AEP-NRC-2021-27, Annual Radioactive Effluent Release Report

Annual Radioactive Effluent Release Report

ML21118B086
Person / Time
Site:	Cook
Issue date:	04/28/2021
From:	Scarpello M Indiana Michigan Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP-NRC-2021-27
Download: ML21118B086 (165)

Text

Indiana Michigan Power INDIANA Cook Nuclear Plant MICHIGAN One Cook Place POWER- Bridgman, Ml 49106 indianamichiganpower.com An MP Company BOUNDLESS ENERGY-April 28, 2021 AEP-NRC-2021-27 10 CFR 50.36a Docket Nos.: 50-315 50-316 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Units 1 and 2 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT In accordance with Technical Specification 5.6.3, Indiana Michigan Power Company, the licensee for Donald C. Cook Nuclear Plant Units 1 and 2, is providing the Annual Radioactive Effluent Release Report as Enclosure 1 to this letter. This report covers the period January 1, 2020, through December 31, 2020.

This letter contains no new or modified regulatory commitments. Should you have any questions, please contact me at (269) 466-2649.

Michael K. Scarpello Regulatory Affairs Director JMT/mll

Enclosure:

Donald C. Cook Nuclear Plant Units 1 and 2 - 2020 Annual Radioactive Effluent Release Report c: R. J. Ancona - MPSC EGLE - RMD/RPS J.B. Giessner- NRC, Region Ill NRC Resident Inspector R. M. Sistevaris - AEP Ft. Wayne, w/o enclosures J.E. Walcutt-AEP Ft. Wayne, w/o enclosures S. P. Wall - Washington, D.C.

A. J. Williamson - AEP Ft. Wayne, w/o enclosures

ENCLOSURE to AEP-NRC-2021-27 DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 2020 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT

SOURCE DOCUMENT LIST ACTION ITEM NO.

DESCRIPTION 2020 Annual Radioactive Effluent Release Report TIIE FOLLOWING DOCUMENTS HAVE BEEN USED AS SOURCES OF INFORMATION FOR PREPARATION OF THE ATTACHED, COPIES OF TIIESE DOCUMENTS ARE AVAILABLE FOR REVIEW AT TIIE LOCATION SPECIFIED.

NO PAGE SOURCE DOCUMENT DESCRIPTION CURRENT SOURCE PARA. TITLE, NUMBER, REVISION, ETC. DOC. LOCATION (FILE NO., ETC.)

A I Control Room logs PowerView and INPO web page B 2 12-OHP-4021-006-004, Data Sheet I L-20-01

• L-20-103 NDM 1 -OHP-4021-028-005, Data Sheet l; 2-OHP-402l-02S.OOS, Data Sheet l; 1-OHP-4021-028-004, Data Sheet l; 2-OHP-4021-028-004, Data Sheet 1; and 12-OHP-4021-023-002, Data Sheet 1 G-20-01

• G-20-18; l-CPR-20-01

• l-CPR-20-115; and 2-CPR-20-01

• 2-CPR-19-223 Radioactive waste shipments and Processor data C 3 Quarterly Dose Calculations with MIDAS and Site Specific Data and Source Docs in NDM, vendor Analysis or REMP TLDs Vendor flies, and REMP results D 4 Control Room logs PowerView E Al.I-I Documentum PMP-6010-OSD-001 OFF-SITE DOSE tAIJ;;llLAIIQ~ MA~llAL E Al.1-2 PMP-6010-OSD-001 QFF-SITE DQ~E CALCULATION MANUAL Documentum E Al.l-3 Documentum PMP-6010-OSD-OOI OFf-SIIf; DOSE ~A!&YLAIIQ~ Ma~llAL F Al.l-4 12-OHP-4021-006-004, Data Sheet I L-20-01

• L-20-103 NDM G Al.1-5 l -OHP-4021-028-005, Data Sheet I; 2-OHP-4021-028-00S, Data NDM Sheet l; l-OHP-4021-028-004, Data Sheet l; 2-OHP-4021-028-004, Data Sheet I; and 12-OHP-4021-023-002, Data Sheet I G-20-01

• G-20-18; l-CPR-20-01

• l-CPR-20-11S; and 2-CPR-20-01

• 2-CPR-19-223 H Al.1-6 None I Al,1-7 12-THP-6020-ADM-010 Data Sheet 1 NDM J Al.l-8 l -OHP-4021-028-005, Data Sheet 1; 2-OHP-4021-028-00S, Data NDM Sheet 1; 1-OHP-4021-028-004, Data Sheet 1; 2-0HP-4021-028-004, Data Sheet I; and 12-0HP-4021-023-002, Data Sheet 1 G-20-01

• G-20-18; 1-CPR-20-01

• 1-CPR-20-11S; and 2-CPR-20-01

• 2-CPR-19-223 K Al.1-9 Totals from pages Al.1-7 & 8. PMP-6010-OSD-00J OFF-SITE DOSE Documentum

~A1£llLAIIQN MA~UAL (for % or quarterly limit)

L AJ.1-10 12-0HP-4021-006-004, Data Sheet 1 L-20-01

• L-20-103 NDM 12 THP 6020 ADM 010 Data Sheet 1 Vendor Analysis of Quarterly Composites Page 1 of 2

SOURCE DOCUMENT LIST ACTION ITEM NO.

DESCRIPTION 2020 Annual Radioactive Effluent Release Report THE FOLLOWING DOCUMENTS HAVE BEEN USED AS SOURCES OF INFORMATION FOR PREPARATION OF THE ATTACHED.

COPIES OF THESE DOCUMENTS ARE AVAILABLE FOR REVIEW AT fflE LOCATION SPECIFIED.

NO PAGE SOURCE DOCUMENT DESCRIPTION CURRENT SOURCE PARA. TITLE, NUMBER, REVISION, ETC. DOC. LOCATION (FILE NO.,ETC.)

M Al.1-11&12 Totals from page Al.1-10. Limits from 10 CFR Part 20, Appendix Documentum Band PMP-6010-OSD-OOI OFF-SITE DOSE CALCULAIION MANl,lAL N Al.1-13 Radioactive Waste shipments NDM 0 At.1-14 Yearly totals and 0/o of PMP-6010-OSD-001~ OFF-SITE DOSE Documentum tALtlJ:LAIIQt'i MAt'ilJ:4L p Al.l-15 Site Specific Data for Site Boundary Distances NDM Q At.2-1

• 4 Quarterly Dose Calculations with MIDAS and Site Specific Data Source Docs In NDM PMP-6010-OSD--OOJ, OFF-SITE DOSE CALCULATION MANUAL R Al.3-1

• 6 GPI Sample Data NDM s Al.1-1

• 8 MIDAS System with Site Specific Data, Meteorological Joint Frequency IT Network drive Tables Al.2-1

• 8 Al.J-1

• 8 Al.4-1

• 8 T AJ.0-1 Off-Site Dose Calculation Manual Revision Documentum Page 2 of 2

TABLE OF CONTENTS Page Table of Contents I. Introduction 1 II. Radioactive Releases and Radiological Impact on Man 1 Liquid Releases 2 Gaseous Releases 2 Solid Waste Disposition 2 III. Meteorological 3 IV. Offsite Dose Calculation Manual (ODCM) Changes 3 V. Total Dose 3 VI. Radiation Monitors Inoperable Greater Than 30 Days 4 VII. Noteworthy Conditions Identified in 2020 s VIII. Conclusion 7 IX. Errata 7 LIST OF APPENDICES Appendix Title Al.I 2020 Effluent and Waste Disposal Annual Report - Supplemental Information Al.2 Summary of Maximum Individual Doses: First Quarter, Second Quarter, Third Quarter, and Fourth Quarter 2020 A 1.3 2020 Groundwater Protection Initiative (GPI) Sample Data A2.1 Hours at Each Wind Speed and Direction: First Quarter, 2020 A2.2 Hours at Each Wind Speed and Direction: Second Quarter, 2020 A2.3 Hours at Each Wind Speed and Direction: Third Quarter, 2020 A2.4 Hours at Each Wind Speed and Direction: Fourth Quarter, 2020 A3.0 Offsite Dose Calculation Manual (ODCM) Changes i

I. INTRODUCTION This report discusses the radioactive discharges from Unit 1 and Unit 2 of the Donald C. Cook Nuclear Plant (CNP) during 2020. This is in accordance with the requirements of CNP Technical Specification (TS) 5.6.3.

The table below summarizes the pertinent statistics concerning the Plant's operation during the period from January 1, 2020, to December 31, 2020. The data in this table and the descriptive information on plant operation are based upon the respective unit's Monthly Operating Reports, Performance Indicators, and Control Room Logs for 2020.

Parameter Unit I Unit2 Gross Electrical Energy Generation 8,586,090 10,252,710 (Me~awatt Hour (MWH))

Unit Service Factor 91.7 95.9 (Percent (%))

Unit Capacity Factor 91.8 97.1 (Maximum Dependable Capacity (MDC)) Net(%)

Unit 1 entered the reporting period in Mode 1 at Nominal Full Power (NFP). Small power adjustments were made to facilitate main turbine valve testing throughout the year. The unit performed a normal downpower and was manually tripped on September 19, 2020, entering refueling outage U 1C30. The unit attained criticality on October 18, 2020, and returned to NFP on October 23, 2020. The unit exited the reporting period at NFP.

Unit 2 entered the reporting period in Mode 1 at Nominal Full Power (NFP). Small power adjustments were made to facilitate main turbine valve testing throughout the year. The unit performed a rapid downpower and was manually tripped on May I, 2020, to perform repairs for Reactor coolant leakage. The unit attained criticality on May 10, 2020, and attained NFP on May 12, 2020. The unit was manually tripped on September 4, 2020, to perform repairs on Pressurizer Spray controls. The unit attained criticality on September 7, 2020, and attained NFP on September 10, 2020. The unit was automatically tripped on October 12, 2020, due to lowering Steam Generator water level resulting from degraded condenser vaccum. The unit attained criticality on October 13, 2020, and attained NFP on October 15, 2020. The unit exited the reporting period at NFP.

II. RADIOACTIVE RELEASES AND RADIOLOGICAL IMPACT ON MAN Since a number of release points are common to both units, the release data from both units are combined to form this two-unit, Annual Radioactive Effluent Release Report (ARERR).

Appendix A1.1 through A2.4 of this report present the information in accordance with Section 5.6.3 of Appendix A to the Facility Operating Licenses, as specified in the Technical Specifications, Regulatory Guide 1.21, and 10 CFR Part 50, Appendix I.

The "MIDAS System" is a computer code that calculates doses due to radionuclides that were released from the CNP.

All liquid and gaseous releases were well within Offsite Dose Calculation Manual (ODCM) limits and federal limits.

There were no abnormal liquid or gaseous releases in 2020. There were no spills or leaks of radioactive liquids requiring voluntary notifications per the Industry Groundwater Protection Initiative or site procedures.

The Independent Spent Fuel Storage Installation (ISFSI) impacts are included with Unit 1 and Unit 2 statistics. The ISFSI cask system does not create any radioactive materials or have any radioactive waste treatment systems. Therefore, specific operating procedures for the control of radioactive effluents are not required. Technical Specifications for the HI-Storm 100 Cask System, Specification 3.1.1, Multi-Purpose Canister (MPC), provides assurance that there are not radioactive effluents from the ISFSI.

Liquid Releases During 2020 there were 99 liquid batch releases performed. The number of liquid batch releases for the 1st, 2nd , 3rd, and 4th quarters in 2020 were 13, 29, 32, and 25, respectively.

Estimated doses (in mrem) to maximally exposed individuals via the liquid release pathways are given in Appendix Al.2 of this report.

Gaseous Releases During the first quarter of2020 there were three batch releases from Gas Decay Tanks (GOT) and 124 Containment Pressure Reliefs (CPR). During the second quarter there were four batch releases from GDTs, two containment purges, and 80 CPR. During the third quarter there were two batch releases from GDTs, one system tank vent, one containment purge, and 66 CPR. During the fourth quarter there were five batch releases from GDTs and 68 CPR.

The CPR continue to be listed as batch releases as described in Nuclear Regulatory Commission Inspections 50-315/89016 (DRSS); 50-316/89017 (DRSS) for CNP, dated June 1, 1989. Doses continue to be calculated utilizing continuous criteria as allowed by NUREG-0133. There were a total of fourteen GDT releases, three containment purge, one system tank vents, and 338 CPR gaseous batch releases made during 2020.

In calculating the dose consequences for continuous and batch gaseous releases during 2020, the meteorological data measured at the time of the release were used.

The estimated doses (in mrem) to maximally exposed individuals via the gaseous release pathways are given in Appendix Al .2 of this report. For individuals that are within the site boundary, the occupancy time is sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary.

Solid Waste Disposition There were 16 shipments of radioactive waste made during 2020. These included shipments made from the site to various radioactive waste processors for ultimate disposal.

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III. METEOROLOGICAL Appendices A2. l, A2.2, A2.3, and A2.4 of this report contain the cumulative joint frequency distribution tables of wind speed and wind direction, corresponding to the various atmospheric stability classes for the first, second, third, and fourth quarters of 2020. Hourly meteorological data is available for review and/or inspection upon request.

IV. OFFSITE DOSE CALCULATION MANUAL {ODCM} CHANGES The ODCM, PMP-601 0-OSD-00 I, was revised during the report period. A revised copy is included and contains a description of the changes.

V. TOTALDOSE Section 3.2.5 of the ODCM requires that the dose or dose commitment to a real individual from all uranium fuel cycle sources in Berrien County be limited to no more than 25 mrem to the total body or any organ (except the thyroid, which is limited to no more than 75 mrem) over a period of 12 consecutive months to show conformance with the requirements of 40 CFR Part 190. The maximum cumulative dose to an individual from liquid and gaseous effluents during 2020 was well within the ODCM limits. Measurements using thermoluminescent dosimeters (TLD) at 12 onsite stations indicate that the dose due to direct radiation is consistent with preoperational and current control (background) levels. This is fully evaluated in CNP's 2020 Annual Radiological Environmental Operating Report.

Additional TLD dosimetry installed by Radiation Protection department programs monitor dose received by individuals on site as visitors.

The annual dose to the maximum individual will be estimated by first summing the quarterly total body air dose, the quarterly skin air dose, the quarterly critical organ dose from iodines and particulates (l&P), the quarterly total body dose from liquid effluents, the quarterly critical organ dose from liquid effluents, and the Radiological Environmental Monitoring Program onsite direct radiation TLD data. These quarterly values are summed with the annual Carbon-14 dose and compared to the annual total body limit for conservative reasons.

The table that follows here represents the above written description:

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Dose (mrem} 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr l&P 1.73E-02 2.86E-02 3.95E-02 1.64E-02 Total Body Air 7.70E-05 2.60E-04 6.90E-04 2.00E-04 Skin 1.20E-04 4.10E-04 1.10E-03 3.30E-04 Liauld TB 3.84E-03 2.95E-02 4.08E-02 1.46E-02 Liauid Oraan 3.84E-03 2.95E-02 4.0SE-02 1.47E-02 Direct Radiation 0 0 0 0 Quarterlv Dose Total 2.52E-02 8.83E-02 1.23E-01 4.62E-02 Sum of Quarter Doses 2.83E-01 C14 (Annual} Dose 2.33E+00 Grand Total Dose (Total Body or any other Oraan) mrem 2.61E+00 Annual Dose Limit (mrem) 25 Percent of limit 1.05E+01 The following data reflects a comparison between 2019 annual dose data and 2020 annual dose data. This indicates that 2020 annual dose was 'typical' in regards to radioactive effluents. The table is presented as follows:

Annual Dose (mrem) %of limit 2019 2.37E+00 9.49 2020 2.61E+00 10.5 VI. RADIATION MONITORS INOPERABLE GREATER THAN 30 DAYS The Radiation Monitor System (RMS) has undergone an extensive replacement project to upgrade and modernize the equipment to support the expected operational lives of the two Cook Plant units. Three effluent monitors (and six area monitors for completeness) were inoperable entering 2020, with the Unit I Vent Stack 1-VRS-1500 and Unit 2 ESW monitors 2-WRA-714/ 2-WRA-718 being all out for more than 30 days. The appropriate compensatory sampling actions were taken throughout the year as releases on these pathways continued. The monitors were being upgraded and modernized, and this inoperable time period > 30days was planned for/ expected due to having to install all the hardware, wiring backbone, network, and displays. The RMS replacement project did significant work in 2020, with the table below providing the details on when work was started (starting the 30 day clock) and when it was returned to service. All were greater than 30 days and all had appropriate compensatory sampling actions or surveys performed throughout the duration.

All effluent releases complied with ODCM requirements. The list includes some area radiation monitors which are not involved with effluent pathways, but are included for completeness. RMS Project work continued into 2020 and was completed on April 14, 2020, concluding the RMS Replacement Project. The table lists all monitors replaced and their times of inoperability.

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1-WRA*713 East Essential Service Water Header Effluent S: 1/15/19 F:9/11/19 1-WRA-717 West Essential Service Water Header Effluent S: 1/15/19 F:9/11/19 12-RRC-330 Spent Fuel Pit Area S: 12/18/18 F: 9/11/19 1-CRA-415 East Component Cooling Loop S:3/14/19 F:9/11/19 1-CRA-425 West component Cooling Loop S: 3/12/19 F:9/11/19 12-ERA-7000 Nuclear Sampllng Room Area S: 12/3/18 F:9/19/19 1-ERA-7300 Aux Building Equipment Room S: 1/28/19 F:9/19/19 1-ERS-7400 Control Room, Instrument Room, and Aux building Area S: 3/12/19 F: 9/19/19 12-ERA-7500 Aux Bull ding Elevation 573' and 587' Area 5: 1/2/19 F:9/19/19 12-RRS-1000 Waste Disposal Liquid Effluent S: 7/8/19 F: 11/7/19 l*MRA-1600 5G land 4 PORVs S:7/8/19 F: 11/21/19 1-MRA-1700 SG 2 and 3 PORVs S:7/8/19 F: 11/21/19 1-VRS-1200 Upper Containment Area S: 7/8/19 F: 11/21/19 1-ERS-1400 Lower Containment Area S:7/8/19 F: 11/21/19 2-DRA-300 SG 8low~own Pre-treatment Effluent S:6/11/19 F: 12/4/19 2-0RA-353 SG Blow~own Post-treatment Effluent S: 6/11/19 f: 12/4/19 2-CRA-415 East Component Cooling Loop S:6/11/19 F: 12/4/19 1-VRS-1500 Unit Vent Effluent S: 8/19/19 F: 1/17/20 1-SRA-1800 Gland Steam Leak off Vent S:8/19/19 F: 12/18/19 1-SRA-1900 Steam Jet Air Ejector Vent S:9/30/19 F: 12/18/19 12-ERA-7600 Aux Building Eleva ti on 633' and 650' Area S:8/19/19 F:12/18/19 2-WRA-714 East Essentlal Service Water Header Effluent S:6/11/19 F: 1/23/20 2-WRA*718 West Essentlal Service Water Header Effluent S: 6/11/19 F: 1/23/20 2-CRA-425 West Component Cooling Loop S:6/11/19 F: 1/23/20 1-VRS-1100 Upper Containment Area S: 12/3/19 F: 4/7/20 1-ERS-1300 Lower Containment Area S: 12/3/19 F:4/7/20 2-VRS-2200 Upper Containment Area S: 11/25/19 F: 2/7/20 2-ERS-2400 lower Containment Area S: 11/25/19 F: 2/7/20 2-ERA-8300 Aux Bulldlng Equipment Room S: 10/8/19 F: 2/13/20 2-ERS-8400 Control Room, Instrument Room, and Aux BulldlngArea S: 12/2/19 F:2/13/20 2-VRS-2500 Unit Vent Effluent S: 2/11/20 F: 4/14/20 2-SRA-2800 Gland Steam leak off Vent S: 2/20/20 F:4/14/20 2-SRA-2900 Steam Jet Air Ejector Vent S:2/20/20 F:4/14/20 2-MRA-2700 SG 2 and 3 PORVs S: 1/23/20 F:4/14/20 2-VRS-2100 Upper Con ta lnment Area S:2/20/20 F:4/14/20 2-MRA-2600 SG 1 and 4 PORVs S: 1/21/20 F:4/14/20 2-ERS-2300 Lower Containment Area S: 2/12/20 F: 4/14/20 The RMS Project completion did result in several technical issues identified as the systems were put into nonnal usage with changing plant conditions. The new detectors were found to be considerably more sensitive to background radiation, resulting in modifications being required to increase shielding of those impacted detectors.

One effluent monitor pathway continues to have issues with the background radiation levels due to the detector sensitivities. 12-RRS-1001/1021 channels of the Waste Disposal liquid effluent monitors were declared inoperable on July 24, 2020 and are requiring software 5

changes in order to address the higher background detected. All releases on this pathway are complying with ODCM required compensatory actions while the solution is being developed and tested. These detectors remained inoperable to the end of the year.

VII. NOTEWORTHY CONDITIONS IDENTIFIED IN 2020 The RMS Replacement Project initiated physical plant alterations in preparation of upgrading and modernizing the plant's ability to monitor radioactive effluents starting at the end of2018 and completed in 2020. The Offsite Dose Calculation Manual revisions completed in 2020 reflecting the completion of the project.

The usage of compensatory actions and sampling during the time periods for which a pathway's monitor is out of service does create some conserv~tism in the calculations for dose to ensure compliance with all regulations. This may take the form of using maximum design flow rates when a flow instrument is out of service, for example. Another example would be the inability to utilize fans during containment pressure reliefs, resulting in longer times of release to lower the observed pressure as well as more actual relief activities since pressure drops are limited. These conservative assumptions increase the calculated dose, and can be observed in the reporting this year. The increases are relatively small when compared to Carbon-14 dose, which was not affected. These conservatisms were removed as equipment was restored.

VIII. CONCLUSION Based on the information presented in this report, it is concluded that CNP Units I and 2 performed their intended design function with no demonstrable adverse effect on the health and safety of the general public.

IX. ERRATA There was an error identified in an information source document that has been provided in the "Gaseous Releases" information provided in Section II of this Introduction to the Annual Effluent Release Report for 2019. This document identification error was found to go back to 2011 when the template was updated incorrectly and transposed some numbers. The following reference information is the correct source:

Nuclear Regulatory Commission Inspections 50-315/89016 (DRSS); 50-316/89017 (DRSS) for CNP, dated June 1, 1989.

This reference source does not alter any of the reported data or doses, and is being updated here to ensure our documentation points to the correct source letters. This reference would be the correct source for our process of handling containment pressure reliefs and applies back to 2011. There are no other errata noted for 2020.

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2020 Effluent and Waste Disposal Annual Report SUPPLEMENTAL INl'ONIATION Facility: Donald c. Cook Nuclear Plant Licensee: Indiana Michigan Power Company 1 REGULATORY LIMITS l .1 Noble Gases The air dose in unrestricted areas due to noble gases released in gaseous effluents shall be limited to the following:

1.1.1 During any calendar quarter, to S 5 mrad/unit for gamma radiation and~ 10 mrad/unit for beta radiation.

1.1.2 During any calendar year, to S 10 mrad/unit for gamma radiation and S 20 mrad/unit for beta radiation.

1,2 Iodines - Particulates The dose to a member of the public from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than eight days in gaseous effluents released to unrestricted areas shall be limited to the following:

1.2.1 During any calendar quarter to S 7.5 mrem/unit to any organ.

1.2.2 During any calendar year to S 15 mrem/unit to any organ.

l. 3 Liquid Effluents The dose or dose commitment to an individual from radioactive material in liquid effluents released to unrestricted areas shall be limited:

1.3.1 During any calendar quarter to S 1.5 mrem/unit to the total body and to S 5 mrem/unit to any organ.

1.3.2 During any calendar year to S 3 mrem/unit to the total body and to< 10 mrem/unit to any organ.

Al.1-1

2020 Effluent and Waste Disposal Annual Report 1.4 Total Dose The dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to S 25 mrem to the total body or any organ (except the thyroid, which is limited to S 75 mrem) over a period of 12 consecutive months.

2 MAXIMUM PERMISSIBLE CONC&NTRATIONS 2.1 Gaseous Effluents The dose rate due to radioactive materials released in gaseous effluents from the site shall be limited to the following:

2.1.1 For noble gases: S 500 mrem/yr to the total body and S 3000 mrem/yr to the skin.

2.1.2 For all radioiodines and for all radioactive materials in particulate form and radionuclides (other than noble gases) with half-lives greater than eight days: S 1500 mrem/yr to any organ.

The above limits are provided to insure that radioactive material discharged in gaseous effluents will not result in the exposure of an individual in an unrestricted area to annual average concentrations exceeding the limits in 10 CFR Part 20, Appendix B, Table 2, Column 1, 2.2 Liquid Effluents The concentration of radioactive material released at any time from the site to unrestricted areas shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10-4 µCi/ml total activity.

Al,1 - 2

2020 Effluent and Waste Disposal Annual Report 3 AVERAGE ENERGY The average energy (E) of the radionuclide mixture in releases of fission and activation gases as defined in Regulatory Guide 1.21, Appendix B, Section A.3 is not applicable because the limits used for gaseous releases are based on calculated dose to members of the public. Release rates are calculated using an isotopic mix from actual samples rather than average energy.

4 MEASUREMENTS and APPROXIMATIONS of TOTAL RADIOACTIVITY 4.1 Fission and Activation Gases Sampled and analyzed on an 8192 channel analyzer and HpGe detector. Tritium analysis is performed using liquid scintillation counters.

4. 2 Iodines Sampled on iodine adsorbing media, and analyzed on an 8192 channel analyzer and HpGe detector.

4.3 Particulates Sampled on a glass filter and analyzed on an 8192 channel analyzer and HpGe detector. Sr-89 and Sr-90 analyses are performed by offsite vendor.

4.4 Liquid Effluents Sampled and analyzed on an 8192 channel analyzer and HpGe detector. Tritium analysis is performed using liquid scintillation counters. Fe-55, Sr-89 and Sr-90 analyses are performed by an offsite vendor. Ni-63 is also currently being analyzed by the offsite vendor in response to evaluation of the 10 CFR 61 sample results.

Al. 1 - 3

2020 Effluent and Waste Disposal Annual Report 5 BATCH REI,EASES 5.1 Liquid 5,1.1 Number of batch releases:

13 releases in the pt quarter, 2020 29 releases in the 2nd quarter, 2020 32 releases in the 3r<1 quarter, 2020 25 releases in the 4th quarter, 2020 5.1.2 Total time period for batch releases:

31,167 minutes 5.1.3 Maximum time for a batch release:

805 minutes 5,1,4 Average time period for batch release:

315 minutes 5.1.5 Minimum time period for a batch release:

134 minutes 5.1.6 Average stream flow during periods of release of effluent into a flowing stream:

6.89E+5 gpm circulating water Al, 1-4

2020 Effluent and Waste Disposal Annual Report

5. 2 Gaseous 5,2,1 Number of batch releases:

127 releases in the pt quarter, 2020 86 releases in the 2nd quarter, 2020 lQ releases in the 3rd quarter, 2020 ll releases .1.n the 4th quarter, 2020 5,2,2 Total time period for batch releases:

23,239 minutes 5.2.3 Maximum time for a batch release:

354 min\:ltes 5,2.4 Average time period for batch release:

65.3 minutes 5.2.5 Minimum time period for a batch release:

5 minutes Al. 1-f,

2020 Effluent and Waste Disposal Annual Report ABNORMAL RELEASES 6.1 Liquid 6.1.1 Number of Releases:

pt Quarter 2nd Quarter 3rd Quarter 4th Quarter 0 0 0 0 6.1.2 Total activity released (Ci) :

pt Quarter 2nd guarter 3rd Quarter 4th Quarter 0 0 0 0 6.2 Gaseous 6.2.1 Number of Releases:

1~ _9uarter 2nd Quarter 3rd Quarter 4th Quarter 0 0 0 0 6.2.2 Total activity released (Ci) :

1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 0 0 0 0 Al.1-6

2020 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE INuclides Released! Unit 1st Quarter! 2nd Quarter I 3rd Ouarterl 4th Quarterl 11, FISSION GASES H3 I Ci 2.43E+Ol 2 .llE+Ol 1.93E+Ol 1.91E+Ol AR41 Ci KR85 I Ci XE133 Ci XE135 Ci XE131m Ci XE133m Ci XE135m Ci ITotal for Period Ci 2.43E+Ol 2. llE+Ol 1.93E+Ol l,97E+Ol 12, IODINES 1131 Ci 3,93E-06 4.lSE-07 2.BBE-10 I132 Ci

!133 Ci ITotal for Period Ci J.93E-06 4.lSE-07 2.88E-10 13, PARTICULATES MN54 Ci CO60 Ci CS137 Ci

!Total for Period Ci

• DENOTES SUPPLEMENTAL ISOTOPES Al.1-7

2020 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS-GROUND LEVEL RELEASES BATCH MODE INuclides Released! Unit 1st Quarter! 2nd Quarter! 3rd Quarter( 4th Quarter!

11, FISSION GASES HJ Ci l,61E-01 1,59E+OO 2.74E-01 6.66E-02 AR41 I Ci 6,SSE-02 2.12E-01 2,l4E-01 l,41E-Ol KR85 I Ci 2,47E-02 3,0SE-02 1 , 09E-02 l.47E-02 KR85m I Ci l,06E-03 2.09E-05 KR87 Ci l,OBE-03 l<R88 I Ci 1.48E-03 XE133 I Ci 8.00E-03 S,47E-02 3.76£-02 l,07E-04 XE135m I Ci l.61E-04 XE135 I Ci 1.61£-02 8,88E-04 ITotal for Period Ci 2.59E-Ol 1, 91E+00 5,38E-01 2.22E-Ol (2. IODINES 1131 I Ci 3,09E-06 Il32 Ci l.12E-05 1133 I Ci 2. 48E-05 1134 I Ci 5.BlE-06 Il35 I Ci 2.30E-06 (Total for Period I Ci 4.72E-05

• DENOTES SUPPLEMENTAL ISOTOPES At. 1-8

2020 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS-GROUND LEVEL RELEASES BATCH MODE INuclides Released! Unit 1st Quarter! 2nd Quarter! 3rd Quarter! 4th Ouarterl

13. PARTICULATES CR51 Ci l.87E-05 C058 Ci 4.32E-05 CO60 Ci l.12E-05 N895 Ci 4.90E-06

!Total for Period Ci 7.BOE-05

• DENOTES SUPPLEMENTAL ISOTOPES Al. 1-!)

2020 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Units 1st I 2nd I 3rd I 4th IEst.

I Quarter I Quarter I Quarter I Quarter ITotal I I I I )Error,tf IA,IFISSICN AND I I !ACTIVATION GASES I 11,fTotal Release I Ci I 9.82E-021 3.16£-011 2,67E-011 l.55E-Oll 13.1 12,IAverage release luCi/secl 1.25£-021 4.02£-021 3.36E-021 1,95E-021 I I rate for period I I I I I I 13,IPercent of 1% Gammal 1.27£-031 6,05£-031 1.20£-021 3.27E-031

!applicable limit' I Beta I 2.84E-041 1.32£-031 2.~lE-031 6.SOE-041 1B. I IODINES I 1. I Total I-131 I Ci I O.OOE+OOI 7. 02£-061 4.lSE-071 2.88E-101 18.4 12,IAverage release luCi/secl O.OOE+OOI 8.92E-071 5,22E-081 3.63E-lll I Irate for period I I I I I I

13. I Percent of I -~ I O.OOE+OOI 2.54E-061 1.49E-071 l.03E-101 I !applicable limit' I I I I I IC, IPARTICULATES 11,IParticulates withl Ci I O.OOE+OOI 7.BOE-051 O.OOE+OOI O.OOE*OOI 15,6 I I lhalf lives>8 days! I I I I I I 12, !Average release luCi/secl O.OOE+OOI 9.92E-061 O.OOE+OOI O.OOE+OOI I Irate for period I I I I I I 13,IPercent of I \ I O.OOE+OOI l.96E-051 O.OOE+OOI O.OOE+OOI I !applicable limit' I I I I I I

14. I Gross alpha I Ci 1<8.35E-071<9.69E-07 <l.55E-061<1,13E-06 1 I !radioactivity I I I I I ID. ITRITIUM 11.ITotal Release I Ci I 2.44E+Oll 2,27E+Oll 2.18E+Oll l.98E+Oll 19.5 t2.1Average release luCi/sec 3.llE+OOI 2.89E+001 2,14E+OOI 2,49E+OOI I Irate for period I I I I I 13,IPercent of I \ I 1.11£-021 1.65E-021 1.56E-021 1.42E-021 I !applicable limit" I I I I

• Applicable limits are expressed in terms of dose. See Appendices Al,2-1 through Al.2-4 Al.1-10

2020 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS CONTINUOUS MODE INuclides Released! Unit 1st Quarter! 2nd Quarterl 3rd Ouarterl 4th Quarter!

HJ I Ci 8,81E-03 BATCH MODE INuclides Released! Unit 1st Quarter! 2nd Quarter! 3rd Quarter! 4th Quarter!

H3 Ci 1.11E+02 1. OSE+OJ l,06E+03 4,27E+02 CR51 Ci 6.JSE-05 MN54 Ci J.24E-04 6, 71E-05 C057 Ci 1.44E-05 3.09E-06 COSS I Ci 2,57E-05 J.37E-05 5.lOE-04 4,56E-04 C060 Ci 9,71E-05 2 .16E-05 5.07E-03 l,OlE-03 NI63 Ci 2,56E-05 2.0SE-03 4,19E-04 ZN65 Ci 1. 71E-04 3.22E-05 ZR95 Ci 2.45E-05 2. 77E-05 NB95 Ci 3.85E-05 4.82E-05 M099 I Ci 2.60E-05 TC99m Ci 2.SOE-05 2.21E-06 AGllOm Ci 2.SJE-04 5,36E-05 SB124 Ci l.lSE-05 3.92E-06 5.52E-06 5B125 I Ci 8 . 70£-05 7.84E-05 2,31E-04 7.82E-05 CS134 Ci CS137 I Ci 2.04E-06 1131 Ci 7.02E-07 1133 I Ci 9.36E-07

• SN113 Ci 9.00E-06 Ci 5,83E-07 "XE133 Ci 4,91E-05 1.78E-04 l.49E-04

• XE135 I Ci

• DENOTES SUPPLEMENTAL ISOTOPES Al.1-11

2020 EFFLllENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS-SUMMATION OF ALI RELEASES BATCH MODE Units 1st 2nd 3rd 4th I Est.

I Quarter I Quarter I Quarter I Quarter ITotal I I I I I Error, ~ I IA. !FISSION AND I !ACTIVATION I !PRODUCTS 11,ITotal Release I Ci I 1.60E-041 2,88E-04 1 8.71E-031 2.27E-031 11.7 12 . tAveragc diluted luCi/ml 2.86E-lll 1,04E-lll 2.76E-101 1,39E-101 I !concentration I I I I I I !during period I I I I 13,IPercent of I I l,67E-041 6,55E-051 5.83E-031 2,37E-031 I !applicable limit I ' I I I I I I B. I TRITIUM 11, !Total Release I Ci I l,11E+021 1,05E+031 l.06E+031 4.27E+021 10,1

12. !Average diluted luCi/ml l.99E-05I 3.79E-051 3.35£-051 2.61E-051 I I concentration I I I I I I I during period I I I I I 13,IPercent of ,. I l . 99E+OOI 3.79E+OOI 3.35E+OOI 2.61E+00 )

I !applicable limit I I I I I I

)C, )DISSOLVED AND I )ENTRAINED GASES Jl. !Total Release I Ci I O.OOE*OOI 5.84E-051 l,79E-041 l.58E-041 12.9 I 12.)Average diluted JuCi/ml O.OOE+OO) 2.llE 121 5.68E-121 9.66E-12 I )concentration I I I I I I !during period I I I I I 13.JPercent of I O.OOE+OOI 1.0SE-061 2.84E-061 4.BJE-061 I !applicable limit I I

' I I I I I ID, I GROSS ALPHA Ci 1<7.08E-051<5,58E-041<1.75E-041<1,39E-041 NIA I !RADIOACTIVITY I I I I I I !TOTAL RELEASE I I I I I IE,IVOLUME OF WASTE I Liters! 7.63E+051 6,01E+06l 1.89E+061 1,50E+061 2.00 I I )RELEASED I I I I I I I IF,IVOLUME OF Liters) 5.59E+091 3.0lE+lll 3, 15E+l01 1. 64E+10 I 3.48 I !DILUTION WATER I I I I I I I USED DURING I I I I I I I PERIOD I I I I I Al. 1-12

2020 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Ll OUID EFFLUENTS-SUMMATION OF ALL RELEASES CONTINUOUS MODE Units 1st 2nd 3rd 4th I Est.

I Quarter Quarter I Quarter I Quarter !Total I I I IError,11 IA, I FISSION AND I I ACTIVATION I (PRODUCTS

11. !Total Release I Ci I O.OOE+OOI O,OOE+OOI O,OOE+OOI O.OOE+OOI N/A 12,IAverage diluted luCi/ml O.OOE+OOI O.OOE+OOI O.OOE+OOI O.OOE+OOI I tconcentration I I I I I I !during period I I I I I 13,IPercent of I I O.OOE+no1 o.OOE+OOI o.OOE+OOI O.OOE+OOI I !applicable limit I I I I I I 18, ITRITIUM

11. !Total Release I Ci O.OOE+OOI 8,81E-031 O.OOE+OOI O.OOE +OOI 56.4

12. !Average diluted luCi/ml 0,00E+OOI 1.lOE-111 O,OOE+OOI O.OOE+OOI I Iconcentration I I I I I I !during period I I I I I

13. I Per cant of O.OOE+OOI 1.lOE-061 O,OOE+OO( O.OOE+OOI I !applicable limit I ' I I I I IC, I DISSOLVED AND I !ENTRAINED GASES 11, I Total Release I Ci I O.OOE+OOI O.OOE+OO( O.OOE+OOI O.OOE+OOI N/A 12,IAverage diluted luCi/ml O.OOE+OOI O.OOE+OOI O.OOE+OOI Q.OOE+OOI I I concentration I I I I I I !during period I I I I I (3. I Percent of I I O.OOE+OOI O.OOE+OOI O.OOE+OOI O.OOE+OOI I !applicable limit I I I I I I ID,IGROSS ALPHA Ci O.OOE+001<3.97E-041 o.OOE+o ~, O.OOE+OOI N/A I !RADIOACTIVITY I I I I I !TOTAL RELEASE I I I I IE,IVOLUME OF WASTE I Litersl O.OOE+OOI 4.28E+061 O,OOE+OOI O.OOE+OOI 2,00 I I I RELEASED I I I I I I I IF. IVOLUME OF Liters I O.OOE+OOI 8,04E+lll O.OOE+OOI O.OOE+OOJ 3.48 I I DILUTION WATER I I I I I I I USED DURING I I I I I I !PERIOD I I I I I Al,l-13

2020 Effluent and Waste Disposal Annual Report Solid Waste and Irradiated Fuel Shipments Solid Waste Shipped Offsite for Burial or Disposal

1) Type of Waste Unit Estimated amount Estimated Total Error,%

a) Spent resins, filters, sludge, m' 1.8SE+01 1.00E+OO evaporator bottoms, etc. Curles 1.94E+02 3.75E+OO b) Dry compressible waste, ml 3.66E+02 1.00E+OO contaminated equipment, etc. Curies 2.26E-01 6.48E+OO m'

c) Irradiated components, control Curles rods, etc.

d) Other (contaminated soll) m' Curles

2) Estimate of Principle Radionuclide Composition

8) H-3 12% Co-58 2% Sb-125 1% Cs-137 I_~%

Mn-54 2% Co-60 10% Cs-134 4%

Fe-55 8% Ni-63 52% C-14 1%

b) Cr-51 1% Co-58 8% Sb-125 1%

Mn-54 2% Co-60 24% Zr/Nb-95 4%

Fe-55 21 o/o Ni-63 29% Cs-137 9% C-14 1%

3) Solid Waste Disposition No. of Shipments Mode of Transoortatlon Destination 8 Truck Oak RidM , TN L . Truck Andrews TX - -*-*- Truck GalnesvlUe,_Fl

4) Type of Containers used for Shipment: Containers used are excepted packages, Type A, Sea Land, metal boxes drums, tankers and hi h lnte rl containers HICs .

1s) Solldlficalion Agent: There were no solidifications performed during this report period.

2020 Effluent and Waste Disposal Annual Report Yearly Release Rates GASES Fission and Activation Oases Total Release 8.36E-Ol Curies Average Release Rate 2.65E-02 µCi/sec

% of Applicable Limits* y l.13E-02 %

~ 2.23E-03 %

Iodines Total 1-131 Release 7.44E-06 Curies Average Release Rate 2.36E-07 µCi/sec

% of Applicable Limit

• 3.39E-0l %

Particulates Total Release 7.80E-0S Curies Average Release Rate 2.47E-06 µCi/sec

% of Applicable Limit* 3.39E-0l %

LIQUIDS Fission and Activation Products Total Release l.l4E-02 Curies Average Diluted Concentration J.41E-10 µCi/ml

% of Applicable Limits. Total Body 1.48E+OO %

Organ 4.44E-Ol %

• Applicable limits are expressed i n terms of the annual 10 CFR 50, Appendix I, dose limits.

Al.I-JS

Site Boundary and Hearest Rasidence Listing The following distances were used in the calculation of the maximum individual doses!

Sector Direction Boundary (Meters) Nearest Residence (Meters)

A N 651 659 B NNE 617 660 C NE 789 943 D ENE 1497 1747 E E 1274 1716 F ESE 972 1643 G SE 629 1640 H SSE 594 964 J s 594 997 K SSW 629 942 l\l.l - 16

Summary of Maximum Individual Doses First Ouarter 2020 EFFLUENT APPLICABLE ESTIMATED AGE LOCATION o/oOF LIMIT ORGAN DOSE(mrem) GROUP DISTDIR(M) APPLICABLE (mrtm)

(Toward) LIMIT QTR Liquid Total Body 3.84E-03 Child Receptor I l.28E-Ol I.SE+0 Liquid 01-LLI 3.84E-03 Child Receptor 1 3.85E-02 5.0E+0 Noble Gas Air Dose 1.27E-04 Any 651 (N) 1.27E-03 S.0E+0 (Gamma-rnrad) Age Noble Gas Air dose S.61E-OS Any 594(S) 2.84E-04 1.0E+l (Beta-mrad) Age Iodines and Total Body l.73E-02 Child 6S9(N) l.lSE-01 7.SE+0 Particulates Al.2-t

Summary of Maximum Individual Doses Second Ouarter 2020 EFFLUENT APPLICABLE ESTIMATED AGE LOCATION o/eOF LIMIT ORGAN DOSE(mrem) GROUP DISTDIR(M) APPLICABLE (mrem)

(Tewani) LIMIT QTR Liquid Total Body 2.9SE-02 Child Receptor 1 9.SOE-01 I.SE+o Liquid Liver 2.9S£-02 Child Receptor I 2.9SE-Ol S.OE+O Noble Gas Air Dose 6.03E.04 Any 629(SSW) 6.0SE-03 S.OE+O (Gamma-mrad) Age Noble Gas Air dose 2.64E-04 Any 629(SSW) l.32E.03 I.OE+l (Beta-mrad) Age Iodines and Total Body 2.86E-02 Child 1747(ENE) 1.91E-01 7.SE+0 Particulates Al .2-2

Summary of Maximum Individual Doses Third Quarter 2020 EFFLUENT APPLICABLE ESTIMATED AGE LOCATION %OF LIMIT ORGAN DOSE(mrem) GROUP DISTDIR(M) APPLICABLE (mrem)

(Toward) LIMIT QTR Liquid Total Body 4.0SE-02 Child Receptor 1 1.36E+OO I.SE+O Liquid 01-LLI 4.0BE-02 Child Receptor I 4.0SE-01 S.OE+O Noble Gas Air Dose 1.20£-03 Any 651 (N) l.20E-02 S.OE+O (Gamma-mrad) Age Noble Gas Air dose 4.42E-04 Any 651 (N) 2.21E-03 1.0E+l (Bela-mrad) Age Iodines and Total Body 3.95E-02 Child 659 (N) 2.63E-01 7.SE+o Particulates Al.2*3

I Summary of Maximum lndlvldual Doses Fourth ouarter 2020 EFFLUENT APPLICABLE ESTIMATED AGE LOCATION %OF LIMIT ORGAN DOSE(mrem) GROUP DISTDIR(M) APPLICABLE (mrem) froward) LIMIT QTR Liquid Total Body 1.46E-02 Child Receptor 1 4.86E-Ol 1.SE+o Liquid GILLI 1.47£-02 Child Receptor I 1.47E-01 S.OE+O Noble Gas Air Dose 3.27E-04 Any 651 (N) 3.27E-03 S.OEtO (Gamma-mrad) Age Noble Gas Air dose 1.30E-04 Any 6S1 (N) 6.SOE-04 1.0E+l (Beta-mrad) Age Iodines and Total Body 1.64E-02 Child 964 (SSE) 1.09E-01 7.SEtO Particulates Al.2-4

2020 GPI Sample Data Samples analyzed for tritium. Values noted are in microcuries per milliliter (uCi/mL)

Lower Limit of Detection LLD Date MW-22D MW- MW-22S MW-24D MW- MW-24S MW-25D MW-22M 24M 2SM 02/19/2020 <LLD <LLD 02/20/2020 <LLD <LLD <LLD* <LLD <LLD <LLD 06/25/2020 <LLD <LLD*

06/29/2020 <LLD <LLD <LLD <LLD <LLD <LLD OSfl0/2020 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD

• (Note: Wells MW-22 through MW- 27 are multi-port wells installed in the Fall of 2009, with three sample points placed at different depths. Si= Shallow M= Middle D- Deep.)

• (Note: A "*" symbol following a sample result denotes a gamma count was performed. Any gamma results above LLD will be additionally flagged and documented in the analysis section.)

• 2020 GPI Sample Data

• Samples analyzed for tritium. Values noted are in microcuries per milliliter (uCilmL)

• Lower Limit of Detection "' LLD Date MW-25S MW-26D MW- MW-26S MW-27D MW- MW-17S 26M 27M 02/19fl020 <LLD <LLD <LLD <LLD <LLD <LLD <LLD 06/25/2020 <LLD <LLD <LLD <LLD <LLD <LLD <LLD OSfl0/2020 <LLD <LLD <LLD <LLD <LLD <LLD <LLD (Note: Wells MW-22 through MW- 27 are multi-port wells installed in the Fall of 2009, with three sample points placed at different depths. S- Shallow M- Middle D Deep.)

(Note: A "*" symbol following a sample result denotes a gamma count was performed. Any gamma results above LLD will be additionally flagged and documented in the analysis section.)

Al.3*1

2020 GPI Sample Data Samples analyzed for tritium. Values noted are in microcuries per milliliter (uCi/mL)

Lower Limit of Detection = LLD Date W-l W-2 W-3 W-4 W-5 W-6 W-7 W-8 01/14/2020 <LLD <LLD <LLD 01/16/2020 <LLD Ol/23/2020 <LLD <LLD <LLD <LLD 04/07/2020 <LLD <LLD 04/14/2020 <LLD 04/22/2020 <LLD <LLD 07/14/2020 <LLD <LLD <LLD <LLD 07/15/2020 <LLD <LLD <LLD <LLD 10/14/2020 <LLD <LLD 10/20/2020 <LLD <LLD <LLD 10/27/2020 <LLD <LLD <LLD (Note: A "*" symbol following a sample result denotes a gamma count was performed. Any gamma results above LLD will be additionally flagged and documented in the analysis section.)

2020 GPI Sample Data Samples analyzed for tritium. Values noted are in microcuries per milliliter (uCi/mL)

Lower Limit of Detection - LLD Date OW-1 OW-2 OW-4 MW-28 MW-29 95-llA 01/14/2020 <LLD 01/22/2020 I.J4e-6 <LLD 02/19/2020 <LLD <LLD 03/03/2020 <LLD <LLD 04/16/2020 <LLD <LLD 06/24/2020 <LLD <LLD 08/30/2020 <LLD <LLD*

11/09/2020 <LLD <LLD (Note: A "*" symbol following a sample result denotes a gamma count was performed. Any gamma results above LLD will be additionally flagged and documented in the analysis section.)

Al.3-2

2020 GP[ Sample Data Samples analyzed for tritium. Values noted are in microcuries per milliliter (uCi/mL)

Lower Limit of Detection = LLD Date SG*l SG-2 SG-4 SG*S EW-19 MW-20 MW-21 EW-18 01/07/2020 <LLD 01/16/2020 <LLD <LLD 01/28/2020 <LLD <LLD <LLD <LLD 04/14/2020 <LLD <LLD 04/22/2020 <LLD <LLD <LLD <LLD 07/06/2020 <LLD 07/14/2020 <LLD <LLD 07/15/2020 <LLD <LLD <LLD <LLD 10/05/2020 <LLD 10/15/2020 <LLD 10/20/2020 <LLD <LLD <LLD <LLD <LLD (Note: A ..... symbol following a sample result denotes a gamma count was performed. Any gamma results above LLD will be additionally flagged and documented in the analysis section.)

2020 GPI Sample Data Samples analyzed for tritium. Values noted are in microcuries per milliliter (uCi/mL)

Lower Limit of Detection = LLD Date W-9 W-10 W-11 W-12 W-13 W-14 W-15 01/16/2020 <LLD <LLD <LLD <LLD <LLD <LLD 01/23/2020 <LLD 04/07/2020 <LLD <LLD 04/14/2020 <LLD <LLD <LLD <LLD <LLD 07/14/2020 <LLD <LLD <LLD <LLD <LLD <LLD <LLD 10/14/2020 <LLD 10/15/2020 <LLD <LLD <LLD 10/20/2020 <LLD <LLD <LLD (Note: A "*" symbol following a sample result denotes a gamma count was performed. Any gamma results above LLD will be additionally flagged and documented in the analysis section.)

A1.3-3

Analysis of the Sample Data The Groundwater Protection Initiative (GP)) Sample Data for 2020 indicates no groundwater contamination in excess of the reporting threshold of 2.00E-5 uCi/mL for tritium. Gamma spectroscopy was perfonned on all Radiological Environmental Monitoring Program wells quarterly. Those results are not actual GPI results so are not included in the ARERR, but are part ofCNP's 2020 Annual Radiological Environmental Operating Report. There were no positively identified gamma radionuclides from plant effluents detected in any of the GPI well samples, and one well with trace levels of tritium just above detection limits.

The LLD value used for tritium counting of the samples was 9.45E-7. This is well below the required maximum LLD value of 2.00E-6 uCi/mL per the ODCM.

No tritium values were found significantly above LLD for 2020, though values found above the LLD are not abnonnal, unexpected, or inconsistent with past sampling history. The samples observed above LLD historically were expected results from the release oftritiated water into the Absorption Pond, a licensed pathway and part of plant design, or the result of recapture deposition of tritium from licensed radioactive gaseous release points. The 2020 results were within expected parameters considering the reduction in tritium released to the Absorption Pond and typical rainfall recapture of tritium experienced.

Wells located inside the Protected Area of the plant are subject to recapture deposition of tritium and may show occasional sample results above LLD values following rainfalls and snow melt. The results observed in 2020 continue to reflect nonnal expectations and behaviors as they relate to recaptured tritium for the weather conditions observed. Well MW-28 lies close to the vent stacks in the predominant wind directions, so it is expected to observe recaptured tritium from precipitation periodically.

There were impacts from the COVID-19 pandemic on sampling which resulted in slightly lower numbers of samples performed than in previous years. Sampling in support of the NEI 07-07 Groundwater Protection Initiative (GPI) was performed per our plant processes and procedures, though the efforts to prevent exposure of essential plant personnel to potential COVID-19 virus exposure led to reducing some sampling activities during periods of increasing trends in virus hospitalizations and positive test information provided by the State of Michigan. Our focus is always on the safety of our workers and the members of the public, and the Cook Plant management made every effort to keep non-essential personnel offsite if possible and away from essential workers required for safe operation of the plant. The GPI is a voluntary industry initiative, so focus was again made on assuring essential regulatory required activities received priority. ODCM required sampling activities as part of the REMP Program are very similar to the GPI utilizing many of the same wells. This redundancy allowed for the scaling back of the non-essential GPI sampling to help reduce worker risk to virus exposure.

The sample data indicates that no radioactive spills or unidentified leaks have occurred in 2020 impacting groundwater. The sample results indicate proper well placement to ensure the protection of the groundwater and early identification of any abnonnal conditions involving groundwater. This is validated by the demonstrated ability to monitor percolation from the Absorption Pond and recaptured tritium in precipitation, with flow direction and behavior acting as described in the plant licensing documents.

At.3-4

Site: AEP Cook Joint Frequency Distribution Hours at Each Wind Speed and Dircclion Total Period Period or Record

• 1:1. 2020

• 3'3 li2020 1

Eltvatlon: Speed: SPIOM Direction: DIRIOM Lapse: DT60M Stablllty Cl111 A Delta Temperature Extremely Unstable Wind Spud (mpll)

Wind l!lrss1121 l!,j w l:.ll Ah.I! 12.ill > 25 1ml N 16 30 2 0 0 0 48 NNE 2 19 I 0 0 0 22 NE 2 2 0 0 0 0 4 ENE 6 3 0 0 0 0 9 E 13 4 0 0 0 0 17 ESE 5 s 0 0 0 0 10 SE 3 s 0 0 0 0 8 SSE 8 1 6 0 0 0 15 s 4 6 4 0 0 0 14 SSW 2 6 2 2 0 0 12 SW 3 s 8 0 0 0 16 WSW 3 12 8 0 0 0 23 w 0 9 I 0 0 0 10 WNW 2 4 0 0 0 0 6 NW 3 18 0 0 0 0 21 NNW 4 23 1 0 0 0 28 Total 76 152 33 2 0 0 263 Calm Hours not Included above for : Total Period 8 Valid Hours for this Stability Clan for: Total Period 263 Total Hours for Period 2184 A2..1-1

Site: AEP Cook Joint Frequency Distribution Hours at Each Wind Speed and Direction Total Period Period or Reeord

• 1/1/2020 - 3!31/2020 Elevation: Speed: SPIOM Direction: DIRIOM Lapse: DT60M Stablllt)' Clau 8 Delta Temperature Moderately Unstable Wind Speed (mph)

Mod l>lrcstlu l.:J  !.:.I ~  !!:..12 12..:.ll ~ I2t!!

N 2 7 4 0 0 0 13 NNE I 2 0 0 0 0 3 NE 5 I 0 0 0 0 6 ENE 0 0 0 0 0 0 0 E I 2 0 0 0 0 3 ESE 3 0 0 0 0 0 3 SE 2 7 0 0 0 0 9 SSE 2 3 I 0 0 0 6 s 2 3 6 0 0 0 II SSW 1 2 2 I 0 0 6 SW 1 4 4 0 0 0 9 WSW 0 11 J 0 0 0 14 w 1 6 2 0 0 0 9 WNW 1 J 0 0 0 0 4 NW 0 5 0 0 0 0 s NNW 2 12 1 0 0 0 JS Total 24 68 23 0 0 116 Cairn Hours not Included above ror: Total Period 8 VaUd Houra lor thb StabUky Cla11 for: Total Period 116 Total Houn for Period 2184 A2.1-2

Site: AEP Cook Joint Frequency Distribution Hours at Each Wind Speed and Direction Total Period Ptrlod of Record l/112020

• 3,31 12020 Elevation: Speed: SPIOM Direction: DIRIOM Lapst: DT60M Stability Class C Delta Temperature Slightly Unstable Wind SpHd (mph)

>>'.ind Wt11ill11a w  !:.I 8

• 13 13-19 1!.=.ll > 25 Illll N 2 IS 3 0 0 0 20 NNE 3 9 0 0 0 0 12 NE 6 l 0 0 0 0 7 ENE 2 3 0 0 0 0 s E 4 8 0 0 0 0 12 ESE 4 2 0 0 0 0 6 SE I 4 0 0 0 0 s SSE 1 6 3 0 0 0 10 s 0 3 s 0 0 0 8 SSW 0 6 I I 0 0 8 SW 0 11 I 2 0 0 14 WSW l 11 I 0 0 0 13 w l 3 0 0 0 0 4 WNW 0 3 l 0 0 0 4 NW 2 6 0 0 0 0 8 NNW 2 8 l 0 0 0 JI Total 29 99 16 3 0 0 147 Calm Hours not Included above for : Total Period 8 Valid Houra for this Stablllty Cius for: Total Period 147 Total Hours for Period 2184 A2.1-3

Sile: AEP Cook Joint Frequency Distribution Hours at Each Wind Speed and Direction Total Period Perled of Record .. lfl,'2020

• 313)12020 Elevation: Speed: SPIOM Direction: DIRIOM Lapse: DT60M Stability Class D Delia Tcmpcnture Neutral Wind Speed (mpb) mall l!IU!ill!D w  !:.I l-13 ll..:..12  !!:..H UI 1!11.l N 38 S4 24 l 0 0 117 NNE 27 58 2 0 0 0 87 NE 2.S 11 0 0 0 0 36 ENE 13 17 0 0 0 0 30 E 15 14 0 0 0 0 29 ESE 19 27 I 0 0 0 47 SE 17 29 23 0 0 0 69 SSE 30 28 16 I 0 0 7S s 22 49 32 6 0 0 109 SSW 9 34 32 8 0 0 83 SW 3 44 22 2 0 0 71 WSW 4 4S 18 3 0 0 70 w 11 S2 IS 0 0 0 78 WNW .s 37 7 0 0 0 49 NW 12 62 6 0 0 0 80 NNW 18 63 II 0 0 0 92 Total 268 624 209 21 0 0 1122 Calm Hour, nor Included above for : Tolal Period 8 Valid Houn for this Stability Class for: Total Period 1122 Total Hour, for Period 2184 A2.1-4

Sile: AEP Cook Joint Frequency Distribution Hours at Each Wind Speed and Direction Total Period Period of Record a l/li2020 - )i) l/2020 Elevadon: Spetd: SPIOM Direction: DIRIOM Lapse: DT60M Stability Class E Delta Temprtature Slightly Stable Wind Speed (mph) moll Wlls:lli!D J...:j w .l:..U ll.:.12 ~  ?..ll I2l!l N 8 I 0 0 0 0 9 NNE 16 0 0 0 0 0 16 NE 12 1 0 0 0 0 13 ENE s 0 0 0 0 0 s E 18 3 0 0 0 0 21 ESE 16 3 0 0 0 0 19 SE II s 0 0 0 0 16 SSE 17 17 1 0 0 0 3S s 19 37 9 0 0 0 6S SSW 9 17 26 6 0 0 S8 SW 7 28 1 0 0 0 42 WSW 6 19 I 0 0 0 26 w 6 IS I 0 0 0 22 WNW 6 7 0 0 0 0 13 NW 6 12 0 0 0 0 18 NNW 7 s 0 0 0 0 12 Total 169 170 4S 6 0 0 390 Calm Hours not Included above for : Total Period 8 Valid Houn for this Stability Class for: Total Period 390 Total Hours for Period 2184 A2.1-5

Site: AEP Coolt Joint Frequency Distribution Hours at Each Wind Speed and Direc:lion Total Period Period or Rteord

• 1/1 /2020

• 3.1 3112020 Elevatlon: Speed: SPI0M Dlrectloa: DIRIOM Lapse: OT60M Stablllty Class F Delta Temperature Modcralcly Stable Wind Sprtd (mpb)

w.lad lllcts:lll!D J.:J  !:.I 1.:.11 11:.12 !t.:.ll > 25 Tu1!l N I 0 0 0 0 0 1 NNE 3 0 0 0 0 0 3 NE 3 0 0 0 0 0 3 ENE 8 0 0 0 0 0 8 E 11 0 0 0 0 0 11 ESE 4 0 0 0 0 0 4 SE 6 0 0 0 0 0 6 SSE 12 I 0 0 0 0 13 s II 1 0 0 0 0 12 SSW s 0 0 0 0 0 s SW 6 0 0 0 0 0 (j WSW 2 0 0 0 0 0 2 w 2 0 0 0 0 0 2 WNW I 0 0 0 0 0 1 NW 3 0 0 0 0 0 3 NNW 0 0 0 0 0 0 0 Total 78 2 0 0 0 0 80 Calm Houn not Included above ror : Total Period 8 VaUd Houn for this Stability Class for: Total Period 80 Total Houn ror Period 2184 A2.1-6

Site: AEP Cook Joint Frequency Distribution Hours at Each Wind Speed and Direction Total Period Period or Record 1/1/2020 - 3i3112020 Elevation: Speed: SPIOM Direction: DIRIOM Lapse: DT60M Stablllty Class 0 Delta Temperature Extremely Stable Wind Speed (mph)

!:'.loll l!lmlllD LI  !=.I l.=.ll ll..:...12 12!.H ~ I5llll N 0 0 0 0 0 0 0 NNE I 0 0 0 0 0 I NE 2 0 0 0 0 0 2 ENE s 0 0 0 0 0 s E 6 0 0 0 0 0 6 ESE s 0 0 0 0 0 s SE 5 0 0 0 0 0 s SSE 3 0 0 0 0 0 3 s 2 0 0 0 0 0 2 SSW 0 0 0 0 0 0 0 SW 0 0 0 0 0 0 0 WSW 0 0 0 0 0 0 0 w 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 2 0 0 0 0 0 2 Total 31 0 0 0 0 0 31 Calm Hours not Included above for : Total Period 8 Valid Hours for this Stablllty Class for: Total Period 31 Total Hours ror Period 2184 A2.1-7

Site: AEP Cook Joint Frequency Distribution Hours at Each Wind Speed and Direclion Summary or All Stablllty Classes Total Period Period of Record* 11112020

• 313112020 Elevatlon: Speed: SPIOM Direction: DIRIOM Lapse: DT60M Della Temperature Wind Speed (mph) mad Dl[!Sll2D J..:J LI l.:.U .lJ.:J2 ~ ~ '.[gJl1 N 67 107 33 I 0 0 208 NNE 53 88 3 0 0 0 144 NE ss 16 0 0 0 0 71 ENE 39 23 0 0 0 0 62 E 68 31 0 0 0 0 99 ESE 56 37 1 0 0 0 94 SE 45 so 23 0 0 0 118 SSE 73 56 27 1 0 0 157 s 60 99 56 6 0 0 221 SSW 26 65 63 18 0 0 172 SW 20 92 42 4 0 0 158 WSW 16 98 31 3 0 0 148 w 21 85 19 0 0 0 125 WNW 15 S4 8 0 0 0 77 NW 26 103 6 0 0 0 135 NNW 35 111 14 0 0 0 160 Total 675 111S 326 33 0 0 2149 Calm Hours not Included above for : Total Period 8 Variable Direction Hours for: Total Period 0 Invalid Houn for: Total Period 27 Valid Houn for this Stability Cla11 for: Total Period 2149 Total Houn for Period 2184 A2.1*8

Site: AEP Cook Joint Frequency Distribution Hours at Each Wind Speed and Direction Total Period Period of Record

• 41112020

• 6/30i2020 Elevation: Spetd: SPIOM Direction: DIRJOM Lapse: OT60M Stablllty Cius A Della Temperature Ex1remcly Unstable Wind Speed (mph)

Wind ~lmllto l.:.J w l:.Ll llill J2.=.H ~ Im!l N 20 79 13 0 0 0 112 NNE 6 10 I 0 0 0 17 NE 4 0 0 0 0 0 4 ENE 3 5 0 0 0 0 8 E 4 13 I 0 0 0 18 ESE 1 7 2 0 0 0 10 SE s 20 s 0 0 0 30 SSE 0 14 3 0 0 0 17 s 3 10 4 0 0 0 17 SSW 0 2 1 0 0 0 3 SW I 21 6 0 0 0 28 WSW 3 33 3 0 0 0 39 w 0 12 6 0 0 0 18 WNW 4 19 s 0 0 0 28 NW 7 20 3 0 0 0 30 NNW 29 53 5 0 0 0 87 Total 90 318 58 0 0 0 466 Calm Hours not Included above for : Total Period 22 Valid Hours for this Stability Class for: Total Period 466 Total Hours for Period 2184 A2.2-1

Site: AEP Cook Joint Frequency Distribution Hours at Each Wind Speed and Direction Total Period Period of Rtcord = 41112020

• 6.'30,2020 Elevatlon: Speed: SPIOM Direction: DIRIOM Lapse: DT60M Srablllty Cl111 B Delta Temperature Moderately Unstable Wind Speed (mph) malllHmllllB 1.:.J ~ l=.Q .Ll.:.l! ~ > 25 1ml N 8 9 2 0 0 0 19 NNE I 2 1 0 0 0 4 NE 0 0 0 0 0 0 0 ENE J 0 0 0 0 0 1 E 0 7 0 0 0 0 7 ESE 0 2 0 0 0 0 2 SE 1 3 0 0 0 0 4 SSE l 10 l 0 0 0 12 s 0 9 2 0 0 0 11 SSW 0 3 I 0 0 0 4 SW 0 10 s 0 0 0 15 WSW 0 16 0 0 0 0 16 w 0 6 0 0 0 0 6 WNW 2 1 0 0 0 0 3 NW I 0 0 0 0 0 I NNW s 4 I 0 0 0 10 Total 20 82 13 0 0 0 115 Calm Hours not Included above for : Total Period 22 Valid Houn for this Stability Class for: Total Period 11S Total Hours ror Period 2184

Site: AEP Cook Joint Frequency Distribution Hours at Each Wind Speed ilnd Direction Total Period Period of Record = 4_1 1;2020

• 6,'30.*2020 Elevation: Speed: SPIOM Direction: DIRIOM Lapse: DT60M StabUlty Class C Delta Temperature Slightly Unstable Wind Speed (mph)

~IDII Wmll!!D l.:.J w l=.ll ~ 11.:.ll ~ Ia1al N 11 9 J 0 0 0 23 NNE 3 0 0 0 0 0 J NE 3 2 0 0 0 0 s ENE 0 2 0 0 0 0 2 E I 3 0 0 0 0 4 ESE I 1 0 0 0 0 2 SE 3 s 1 0 0 0 9 SSE 3 4 1 0 0 0 8 s 2 4 0 0 0 0 6 SSW I s 1 0 0 0 7 SW 3 10 2 0 0 0 IS WSW 0 6 I 0 0 0 7 w 3 3 0 0 0 0 6 WNW 2 3 1 0 0 0 6 NW I I 2 0 0 0 4 NNW 12 s 1 0 0 0 18 Tolal 49 63 13 0 0 0 125 Calm Houn not lnduded above for : Total Period 22 Valid Hours for this Stability Class for: Total Period 12S Total Hours for Period 2184 A2.2-3

Site: AEP Cook Jolat Frequency Distribution Hours at Each Wind Speed and Direc1ion Total Period Period or RtCGrd

• 4.1 112020 - 6'30.'2020 Elevation: Speed: SPIOM Direction: DIRIOM Lapse: DT60M Stability Class D Delea Temperature Neutral Wind Speed (mpla) mall Rl!mllD w w l.:.U il.:.12 12.:.ll  ?..ll Illll N 39 38 12 0 0 0 89 NNE 18 13 I 0 0 0 32 NE IS 1 0 0 0 0 16 ENE 9 21 0 0 0 0 30 E 17 16 s 0 0 0 38 ESE 14 26 I 0 0 0 41 SE 14 29 0 0 0 0 43 SSE 13 24 2 0 0 0 39 s 14 19 3 0 0 0 36 SSW s 43 16 0 0 0 64 SW 12 30 25 0 0 0 67 WSW 9 13 2 0 0 0 24 w 8 J9 3 0 0 0 30 WNW 3 11 I 0 0 0 15 NW 7 10 3 0 0 0 20 NNW 14 22 7 0 0 0 43 Tolal 211 335 81 0 0 0 627 Calm Houn not Included above for : Total Period 22 Valid Houra for thb StabUlty ClaH for: Total Period 627 Total Hours lor Period 2184 A2.2-4

Site: AEP Cook Joint Frequency Distribution Hours at Each Wind Speed and Direction Total Period Period of Record

• 4l}i2020

• 6!30.'2020 Elevation: Speed: SPIOM Direction: DIRIOM LapH: DT60M Stabnlty Class E Delta Temperature Slightly Stable Wind Speed (mph)

Wied ~lmll!D 1.:.J i::J l.:.ll llill 12.!..ll ~ Illal N 33 13 1 0 0 0 47 NNE 28 II 0 0 0 0 39 NE 29 0 0 0 0 0 29 ENE 13 2 0 0 0 0 IS E 21 8 0 0 0 0 29 ESE 24 4 0 0 0 0 28 SE 19 3 0 0 0 0 22 SSE 31 19 0 0 0 0 so s 36 17 3 0 0 0 S6 SSW 9 12 s 2 0 0 28 SW 11 22 3 0 0 0 36 WSW 6 13 0 0 0 0 19 w 2 s 0 0 0 0 7 WNW s I I 0 0 0 7 NW 8 2 I 0 0 0 11 NNW IS s 0 0 0 0 20 Total 290 137 14 2 0 0 443 Calm Hours not Included above ror : Total Period 22 Valid Hour, for this St* blllty Class for: Total Period 443 Total Hours for Period 2184 A2.2-5

Site: AEP Cook Joint Frequency Distribution Hours at Each Wind Speed and Direction Total Period Period of Rec:ord 41112020 - 6!30/2020 Elevation: Speed: SPIOM Direction: DIRIOM Lapse: DT60M Stablllty Class F Delta Temperatu~ Moderately Stable Wind Speed (mph)

Wind RIWIIAD w w l..:.ll J1.:..l2 ~  ?....U Total N 6 0 0 0 0 0 6 NNE ti 0 0 0 0 0 11 NE 19 0 0 0 0 0 19 ENE 15 0 0 0 0 0 15 E 25 0 0 0 0 0 25 ESE 28 0 0 0 0 0 28

• SE 21 0 0 0 0 0 21 SSE 20 0 0 0 0 0 20 s 16 3 0 0 0 0 19 SSW 3 2 0 0 0 0 5 SW 1 0 0 0 0 0 1 WSW 4 I 0 0 0 0 5 w I 0 0 0 0 0 1 WNW I 0 0 0 0 0 I NW J I 0 0 0 0 2 NNW 7 0 0 0 0 0 7 Total 179 7 0 0 0 0 186 Calm Hour, not lneluded above for : Total Period 22 Valld Hours far this Stability Clan for: Total Period 186 Total Houra (or Period 2184 A2.2-6

Site: AEP Cook Joint Frequenty Distribution Hours at Each Wind Speed and Direclion Total Period Period of Record

• 4/112020 - 6130.-2020 Elevallon: Speed: SPIOM Direction: DIRIOM Lapse: DT60M Stablllly Class 0 Delta Temperature Extremely Stable Wind Speed (mpb)

Wied l!l[tsllon  !.:j i;.I ~ ll.:.12 ~ ~ Imal N 1 0 0 0 0 0 1 NNE 3 0 0 0 0 0 3 NE 13 l 0 0 0 0 14 ENE 26 0 0 0 0 0 26 E 47 0 0 0 0 0 47 ESE 20 0 0 0 0 0 20 SE 14 0 0 0 0 0 14 SSE 24 0 0 0 0 0 24 s 11 0 0 0 0 0 11 SSW 4 0 0 0 0 0 4 SW 5 0 0 0 0 0 s WSW 2 0 0 0 0 0 2 w 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 3 0 0 0 0 0 3 NNW 4 0 0 0 0 0 4 Total 177 0 0 0 0 178 Calm Hours not Included above for : Total Period 22 Valid Hours for this Stablllt)' Class for: Total Period 178 Total Houn for Period 2184 A2.2-7

Site: AEP Cook Joint Frequency Distribution Hours al Each Wind Speed and Direclion Summary or All Stability Classes Total Period Period of Record

• 4 112020 1 - 6!30/2020 Elevation: Speed: SPIOM DJrectlon: DIRIOM LapH: DT60M Delta Tempenilurc Wind Speed (mph) m11sl i!l[ISll!IB ~ ~ l:..U ~  !!.:.ll  ?..ll Illll N 118 148 31 0 0 0 297 NNE 70 36 3 0 0 0 109 NE 83 4 0 0 0 0 87 ENE 67 30 0 0 0 0 91 E 115 47 6 0 0 0 168 ESE 88 40 3 0 0 0 131 SE 77 60 6 0 0 0 143 SSE 92 71 7 0 0 0 170 s 82 62 12 0 0 0 156 SSW 22 67 24 2 0 0 IIS SW 33 93 41 0 0 0 l67 WSW 24 82 6 0 0 0 112 w 14 4S 9 0 0 0 68 WNW 17 35 8 0 0 0 60 NW 28 34 9 0 0 0 71 NNW 86 89 14 0 0 0 189 Total 1016 943 179 2 0 0 2140 Calm Hour* not Included above ror : Total Ptrlocl 22 Variable Direction Hours for: Total Period 0 Invalid Houn for: Total Period 22 Valid Houn for tills Stability Class for: Total Period 2140 Total Noun for Period 2184 A2.2*8

Site: AEP Cook Joint Frequency Distribution Hours at Each Wind Speed and Direction Total Period Period or Record

• 1(112020 - 9 30 '2020 Elevatloa: Speed: SPIOM Direction: OIRI0M Lapse: DT60M Stability Clu1 A Delta Tempcratu" Exttemely Unstable Wind Spetd (mph)

~lad Dlm!loD w w Wl il.:..12 11.:.U  ?..U JJd!l N 41 79 0 0 0 0 120 NNE II 8 0 0 0 0 19 NE s 5 0 0 0 0 10 ENE 2 3 0 0 0 0 s E 3 6 0 0 0 0 9 ESE s 10 0 0 0 0 15 SE 4 4 0 0 0 0 8 SSE 2 12 0 0 0 0 14 s 0 12 2 0 0 0 14 SSW 1 13 4 0 0 0 18 SW 3 34 2 0 0 0 39 WSW 4 24 0 0 0 0 28 w 7 19 0 0 0 0 26 WNW 10 II 0 0 0 0 21 NW 8 7 0 0 0 0 IS NNW 27 32 0 0 0 0 59 Total 133 279 8 0 0 0 420 Calm Noun not Included above ror : Tatal Period 74 Valid Houn ro, this Stablllty Class for: Total Period 420 Total Hour* ro, Period 2208 A2.3-1

Site: AEP Cook Joint Frequency Distribution Hours at Each Wind Speed and Direction Total Period Period of Record

• 711/2020 - 9,130 12020 Elevatloa: Spetd: SPlOM Direction: DlRlOM Lapse: DT60M Stability Cius B Delta Temperature Moderately Unstable Wind Speed (mph)

Wind IHwll!ID w w l..=.ll ~ ~ ~ Im!

N 8 3 0 0 0 0 JI NNE 2 0 0 0 0 0 2 NE I 0 0 0 0 0 l ENE I 0 0 0 0 0 I E I 0 0 0 0 0 I ESE s I 0 0 0 0 6 SE 0 I 0 0 0 *0 I SSE I 2 0 0 0 0 3 s 6 8 3 0 0 0 17 SSW 2 22 7 0 0 0 31 SW 4 18 0 0 0 0 22 WSW 1 s 0 0 0 0 6 w s I 0 0 0 0 6 WNW 3 2 0 0 0 0 s NW 4 0 0 0 0 0 4 NNW s I 0 0 0 0 6 Total 49 64 10 0 0 0 123 Calm Houn not Included abon for : Total Period 74 Valid Hours for this Stability Clau for: Total Period 123 Total Hours for Period 2208 A2.3-2

Site; AEP Cook Joint Frequency Distribution Hours at Each Wind Speed and Direction Total Period Period or Record .. 71112020

• 9130:2020 Elevation: Speed: SPlOM Direction: DIRIOM Lapse: DT60M Stablllty Cius C Della Temperature Slightly Unstable Wind Speed (mph)

~lml IHu"l!D w  !:.I ~ ll.:.J2 .l1.:J5 ~ ~

N 8 8 0 0 0 0 16 NNE I 0 0 0 0 0 1 NE s 2 0 0 0 0 7 ENE I 1 0 0 0 0 2 E s 0 0 0 0 0 s ESE 3 0 0 0 0 0 3 SE s 2 0 0 0 0 7 SSE 3 0 0 0 0 0 3 s 1 6 0 0 0 0 7 SSW 2 7 2 0 0 0 II SW 2 14 I 0 0 0 17 WSW 4 0 0 0 0 0 4 w 1 0 0 0 0 0 I WNW s 0 0 0 0 0 s NW 3 I 1 0 0 0 5 NNW 4 0 0 0 0 0 4 Total 53 41 4 0 0 0 98 Calm Hours not Included above ror : Total Period 74 Valid Hours ror this Stablllty Class for: Total Period 98 Total Houn for Period 2208 A2.3-3

Site: AEP Cook Joint Frequency Dlstribudon Hours at Each Wind Speed and Direction Total Period Period of Record

• 11112020 - 9/30.'2020 Elevation: Speed: SPIOM Direction: DIRIOM Lapse: DT60M S11b1Uty Class D Delta TC111pcra1ure Neutral Wind Speed (mph)

Mn!! Dltectlon w i:J l.:..U ~ 12.:..ll ~ Iml N 60 17 0 0 0 0 77 NNE 25 1 0 0 0 0 26 NE 17 s 0 0 0 0 22 ENE 13 1 0 0 0 0 14 E 9 6 0 0 0 0 IS ESE 13 4 0 0 0 0 17 SE 12 7 0 0 0 0 19 SSE 9 3 0 0 0 0 12 s 13 20 18 0 0 0 Sl SSW 3 57 IS 2 0 0 77 SW 7 52 s 0 0 0 64 WSW s 12 0 0 0 0 17 w 8 4 l 0 0 0 13 WNW 12 4 0 0 0 0 16 NW 7 4 2 0 0 0 13 NNW 18 2 0 0 0 0 20 Total 231 199 41 2 0 0 473 Calm Houra not lncludid above ror : Total Period 74 V1Ud Hourt for this Stability Class for: Total Period 473 Total Ho1&n for Period 2208

Site: AEP Cook Joint Frequency Distribution Hours at Each Wind Speed and Direction Total Period Period of Record

• 7/J/2020 - 9*30,2020 Elevation: Speed: SPIOM Dlrec:don: DIRIOM Lapse: DT60M Stability Cla11 E Del11 Tempcratun: Slightly Stable Wind Speed (mph)

Wind l!ltssdon w  !.:.I l:.ll ll.:..12 1!=.ll ~ ~

N 40 21 0 0 0 0 61 NNE 36 I 0 0 0 0 37 NE 34 1 I 0 0 0 36 ENE 11 0 0 0 0 0 11 E 19 0 0 0 0 0 19 ESE 22 0 0 0 0 0 22 SE 17 0 0 0 0 0 17 SSE 20 0 0 0 0 0 20 s 3S 26 1 0 0 0 62 SSW IS 28 0 0 0 0 43 SW IS 10 0 0 0 0 2S WSW 6 1 0 0 0 0 13 w s 7 0 0 0 0 12 WNW 9 s I 0 0 0 IS NW 8 4 0 0 0 0 12 NNW 13 s 0 0 0 0 18 Total 305 115 3 0 0 0 423 Calm Hours not Included above lor : Total Period 74 Valid Hours lor this Stability Class lor: Total Period 423 Total Hour* for Period 2208 A2.3-5

Site: AEP Cook Joint Frequency Distribution Hours al Each Wind Speed and Direction Total Period Period or Record 11112020

• 9'30/2020 Elevation: Speed: SPIOM Direction: DlRIOM Lapse: DT60M Stablllty Class F Delta Temperature Moderately Stable Wind Speed (mph)

Wlnl1 Dltts!ll!D ~ i:J WJ l1::.l2 ~ ?A Imal N 9 0 0 0 0 0 9 NNIE 6 0 0 0 0 0 6 NE 25 0 0 0 0 0 2S ENE 22 0 0 0 0 0 22 E 32 0 0 0 0 0 32 ESE 28 0 0 0 0 0 28 SE 21 0 0 0 0 0 21 SSE 36 0 0 0 0 0 36 s 33 3 0 0 0 0 36 SSW 10 0 0 0 0 0 10 SW 2 0 0 0 0 0 2 WSW 2 0 0 0 0 0 2 w 4 0 0 0 0 0 4 WNW 2 0 0 0 0 0 2 NW s 0 0 0 0 0 s NNW s 0 0 0 0 0 s Total 242 3 0 0 0 0 245 Calm Houn not Included above ror : Total Period 74 Valld Hours for this Stability a1u ror: Total Period 245 Total Houn for Period 2208 A2.3-6

Site; AEP Cook Joint Frequency Distribution Hours at Each Wind Speed and Direction Total Period Period or Record

• 711/2020 - 913012020 Elevatloo: Speed: SPIOM Dlrtttlon: DIRIOM Lapse: DT60M Stablllty Class 0 Della Temperature Exb'Cmcly Stable Wind Speed (mph)

~ln!I lllmlmn w  !=.! l..:.!2 Jl.:J! .12..:.ll ~ l2ll1 N 2 0 0 0 0 0 2 NNE 2 0 0 0 0 0 2 NE 25 0 0 0 0 0 25 ENE 33 0 0 0 0 0 33 E 64 0 0 0 0 0 64 ESE 40 0 0 0 0 0 40 SE 40 0 0 0 0 0 40 SSE 60 0 0 0 0 0 60 s 52 0 0 0 0 0 52 SSW 19 0 0 0 0 0 19 SW 3 0 0 0 0 0 3 WSW 0 0 0 0 0 0 0 w 2 0 0 0 0 0 2 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW 3 0 0 0 0 0 3 Total 345 0 0 0 0 0 345 Calm Hour* aot Included above for : Total Period 74 Valld Hours ror this Stability Class ror: Total Period 345 Total Hours ror Period 2208 A2..3-7

Site: AEP Cook Joint Frequency Distribution Hours at Each Wind Speed and Direction Summary or All Stablllty Classn Total Period Period or Record .. 7/li2020 - 9.'30!2020

[levatlon: Speed: SPIOM Direction: DIRJOM Lapse: DT60M Delta Temperature Wind SpHcl (mph)

~Ind 121[U1111D w w l.=.U il..:..12 .12.:..ll ~ I2lal N 168 128 0 0 0 0 296 NNE 83 10 0 0 0 0 93 NE 112 13 I 0 0 0 126 ENE 83 s 0 0 0 0 88 E 133 12 0 0 0 0 145 ESE 116 IS 0 0 0 0 131 SE 99 14 0 0 0 0 113 SSE 131 17 0 0 0 0 148 s 140 75 24 0 0 0 239 SSW S2 127 28 2 0 0 209 SW 36 128 8 0 0 0 172 WSW 22 48 0 0 0 0 70 w 32 31 I 0 0 0 64 WNW 41 22 I 0 0 0 64 NW 3S 16 3 0 0 0 S4 NNW 75 40 0 0 0 0 llS Total 1358 701 66 2 0 0 2127 Calm Houn not Included above for : Total Period 74 Variable Direction Hours lor: Total Period 0 Invalid Houn for: Total Period 7 Valid Honn for tills Stablllty Cius for: Total Period 2127 Total Hours for Period 2208 A2.3-8

Site: AEP Cook Joint Frequency Distribution Hours at Each Wind Speed and Direction Total Period Period of Record I0.'1!2020 - 12i31 f2020 Elevallon: Speed: SPIOM Direction: DIRIOM Lapse: DT60M Stablllty Class A Delta Temperature Extremely Unstable Wind Speed (mph)

Wind IIIUSIIIID w i:..l l..::.ll ~ 12..:..U ~ I!ll1 N 2 9 2 0 0 0 13 NNE I 2 0 0 0 0 3 NE 0 I 0 0 0 0 I ENE 0 2 0 0 0 0 2 E 0 4 0 0 0 0 4 ESE 0 2 0 0 0 0 2 SE 0 2 0 0 0 0 2 SSE 0 2 0 0 0 0 2 s 0 0 3 l 0 0 4 SSW 0 0 I 0 0 0 I SW 0 7 3 0 0 0 10 WSW 0 4 2 0 0 0 6 w 0 2 I 0 0 0 3 WNW 0 4 1 0 0 0 s NW I 7 0 0 0 0 8 NNW I II 0 0 0 0 12 Total s 59 13 0 0 78 Calm Hours not Included above for : Tetal Period 3 Valid Hours for this Stability Class for: Tetal Period 78 Total Hours for Period 2208 A2.4-1

Site: AEP Cook Joint Frequency Distribution Hours at Each Wind Speed and Direction Total Period Period or Record

• 10!112020

• 1213112020 Elevation: Speed: SPIOM Direction: OIRI0M l,apte: DT60M Stablllty Clm B Delta Temperature Moderalely Unstable Wind Speed (mph)

Mall Dltssllaa l:j i=-1 .l:..U 11.:.12 12=.ll ~ 11111 N l l 0 0 0 0 2 NNE 0 2 0 0 0 0 2 NE 0 l 0 0 0 0 I ENE 1 1 0 0 0 0 2 E 0 3 0 0 0 0 3 ESE 0 3 0 0 0 0 3 SE 0 0 0 0 0 0 0 SSE 0 6 0 0 0 0 6 s 0 3 II I 0 0 IS SSW 0 3 7 0 0 0 10 SW 0 13 7 0 0 0 20 WSW 0 2 0 0 0 0 2 w 0 s 0 0 0 0 s WNW 0 3 0 0 0 0 3 NW 0 I 0 0 0 0 I NNW I 3 0 0 0 0 4 Total 3 so 25 0 0 79 Calm Houn not Included above for : Total Period 3 Valid Roura for this Stablllly Class for: Total Period 19 Total Hours for Period 2208 A2.4-2

Site: AEP Cook Joint Frequency Distribution Hours at Each Wind Speed and Direction Total Period Period of Rttord

• IO' l i2020

• 12,31 12020 Elevation: Speed: SPIOM Dlmtlon: DIRIOM Lapse: DT60M Stability Class C Della Temperature Slightly Unstable Wind Spttd (mph) mn!IW[ectton J..:j ~ l...:.J1 ~ l!.:.U  ?.ll l!!!I N I 3 0 0 0 0 4 NNE I 3 0 0 0 0 4 NE 0 2 0 0 0 0 2 ENE 0 3 0 0 0 0 3 E I 2 0 0 0 0 l ESE 0 I 0 0 0 0 1 SE I I 0 0 0 0 2 SSE 0 9 1 0 0 0 10 s 0 6 12 I 0 0 19 SSW 0 6 8 J 0 0 IS SW 0 8 s 0 0 0 13 WSW 0 9 I 0 0 0 JO w 2 0 0 0 0 0 2 WNW l 3 0 0 0 0 4 NW 0 6 0 0 0 0 6 NNW 3 l 0 0 0 0 6 Total 10 6S 27 2 0 0 104 Calm Houn not Included abovt ror : Total Period 3 Valid Houn ror this Stability 0111 ror: Total Period 104 Total Hours ror Period 2208 A2.4-3

Site: AEP Cook Joint Frequency Distribution Hours at Each Wind Speed and Direction Total Period Period of Record

• IO't12020

• 12/3li2020 Elevation: Speed: SPIOM Dlrecclon: DIRIOM Lap1t: DT60M St1bW1y Class D Delta Temperature Neu1ral Wind Speed (mpb)

!:'.inlllHmm1a cJ i:.1 l.:.U 11:.12  !!:11 ~ nll1 N 20 43 24 0 0 0 87 NNE 29 8 0 0 0 0 37 NE 23 2 0 0 0 0 25 ENE 19 24 0 0 0 0 43 E 28 19 l 0 0 0 48 ESE 17 8 0 0 0 0 25 SE 24 37 17 0 0 0 78 SSE 19 37 16 1 0 0 73 s 12 45 57 16 0 0 130 SSW 5 46 35 8 0 0 94 SW 3 so 30 s 0 0 88 WSW 6 32 20 9 0 0 67 w 4 31 16 1 0 0 52 WNW ll 34 9 0 0 0 54 NW 13 58 II 0 0 0 82 NNW 10 48 36 0 0 0 94 Total 243 522 272 40 0 0 1077 Calm Hour. not Included above for : Tolal Period 3 Valld Houn for tblt Slablllly aw for: Total Period 1077 Total Houn for Ptrlod 2208 A2.4-4

Site: AEPCook Joint Frequency Distribution Hours at Each Wind Speed and Direction Total Period Period or Record cc 10!]12020

• 12-'31/2020 Elevation: Speed: SPIOM Direction: DIRIOM Lapae: DT60M Stability Clau E Delta Temperature Slightly Stable Wind Speed (mpb) mall 121tts!IRD l.:.J ~ l..:..ll Uill 12.:.ll  ?...ll I!1ll N 28 9 0 0 0 0 37 NNE 26 0 0 0 0 0 26 NE 35 0 0 0 0 0 35 ENE IS 0 0 0 0 0 IS E 22 2 0 0 0 0 24 ESE 24 8 0 0 0 0 32 SE 25 13 2 0 0 0 40 SSE 32 21 15 0 0 0 68 s 12 80 31 1 0 0 124 SSW 12 27 22 I 0 0 62 SW 6 28 13 0 0 0 47 WSW 4 7 1 0 0 0 12 w 6 8 0 0 0 0 14 WNW 11 9 0 0 0 0 20 NW 18 24 I 0 0 0 43 NNW 9 37 0 0 0 0 46 Total 285 273 85 2 0 0 645 C* lm Hours not Included above ror : Total Period 3 Valid Houn for chis Stablllty Class ror: Total Period 645 Tocal Roan ror Period 2208 A2.4-5

Sile: AEP Cook Joint Frequency Distribution Hours at Each Wind Speed and Direction Total Period Period of Record

• 10 1112020

• 12,3112020 Elevation: Speed: SPIOM Direction: DIRIOM Lap11: DT60M Stability Class F Delta Temperature Moderately Stable Wind SpNd (mph)

Wind DJrssll!D J..:.J  !:.I l.:J.l ll.:.12 12=.ll  ?.JJ Il!ll N 2 0 0 0 0 0 2 NNE s 0 0 0 0 0 s NE s 0 0 0 0 0 s ENE 7 0 0 0 0 0 7 E 2 0 0 0 0 0 2 ESE 12 0 0 0 0 0 12 SE 22 3 0 0 0 0 2S SSE 33 13 0 0 0 0 46 s 8 7 0 0 0 0 IS SSW 3 I 0 0 0 0 4 SW l 0 0 0 0 0 I WSW I 0 0 0 0 0 l w 0 0 0 0 0 0 0 WNW I 0 0 0 0 0 I NW 0 0 0 0 0 0 0 NNW I 0 0 0 0 0 l Total 103 24 0 0 0 0 127 Calm Houn nor Included above for: Total Period 3 Valid Hours ror this Stablllty Clw for: Total Period 127 Total Hour, for Period 2208 A2.4-6

Sicc: AEP Cook Joint Frequency Distribution Hours at Each Wind Speed and Direction Total Period Period of Record"' 1011/2020

• 12'3112020 Elevation: Speed: SPIOM Dlrec:tlon: DIRIOM Lapse: DT60M Stability Class G Delta Temperature Extremely Stable Wind Speed (mpb) madRIHlillllD ~ w l:.ll  !!:.I! 12.:..ll ~ Ialll N 0 0 0 0 0 0 0 NNE I 0 0 0 0 0 I NE 3 0 0 0 0 0 3 ENE 9 0 0 0 0 0 9 E 11 0 0 0 0 0 IJ ESE IS 0 0 0 0 0 IS SE 23 1 0 0 0 0 24 SSE 18 0 0 0 0 0 18 s 9 0 0 0 0 0 9 SSW 3 0 0 0 0 0 3 SW I 0 0 0 0 0 I WSW 0 0 0 0 0 0 0 w 0 0 0 0 0 0 0 WNW 0 0 0 0 0 0 0 NW 0 0 0 0 0 0 0 NNW l 0 0 0 0 0 I Total 94 0 0 0 0 9S Calm Hour* not Included above for : Total Period 3 Valld Houn for this StabWty Class for: Total Period 95 Total Hours for Period 2208 A2.4-7

Site: AEP Cook Joint Frequency Distribution Hours at Each Wind Speed and Direc1ion Summary or All Stablllty Clann Total Period Period of Record

• 10:1,2020

• 12/3\/2020 Elevatlon: Speed: SPIOM Direction: DIRIOM Lapse: DT60M Delta Temperature Wind Speed (mpll) mall DIEISIIIIB l:.J i:..I l=.ll ll.ill J2=.U > 25 I!ll1 N 54 6S 26 0 0 0 14S NNE 63 IS 0 0 0 0 78 NE 66 6 0 0 0 0 72 ENE SI 30 0 0 0 0 81 E 64 30 I 0 0 0 9S ESE 68 22 0 0 0 0 90 SE 9S S1 19 0 0 0 171 SSE 102 88 32 1 0 0 223 s 41 141 114 20 0 0 316 SSW 23 83 73 10 0 0 189 SW II 106 S8 s 0 0 180 WSW II 54 24 9 0 0 98 w 12 46 17 I 0 0 76 WNW 24 53 10 0 0 0 87 NW 32 96 12 0 0 0 140 NNW 26 102 36 0 0 0 164 Total 743 994 422 46 0 0 220S Calm Hours not Included above rer : Total Period 3 Variable Dlreellon Houn for: Total Period 0 Invalid Hours for: Tocal Period 0 Valid Houn for this Stability Class for: Total Period 220S Total Hours for Period 2208 A2.4-8

OFF-SITE DOSE CALCULATION MANUAL CHANGES The Off-Site Dose Calculation Manual, PMP-60I0-OSD-001, was revised during this 2020 reporting period. The new revision (#27) was supporting the Radiation Monitor Replacement projects, and went into effect on December 15, 2020. This revision completes the transition, removing the older monitors and leaving just the applicable new replacements. Revision 27 has been attached.

A3.0-l

American Electric Power Service Corporation - Cook Document Info Document Number : PMP-60 I 0-OSD-00 I Revision Number: 027 Title : OFF-SITE DOSE CALCULATION MANUAL Effective Date: 12/ 15/2020 Workflow Info Revision Type: Major Editorial Correction Form Number: CNP-WF-1877 Admin Hold AR #: Type: Procedure CDI/50.59/EC #:

PORC Mtg #: 4824 CARB Mtg#:

Superseding Proc(s):

Training Required: No Verification/Validation Complete: No Approvals Name Review/Approval Date Dave Raye-i728074 Emergency Preparedness - Cross Discipline Review 10/21 /2020 1:26:13 PM Bob Bennett-i059343 Operations - Cross Discipline Review 10/21 /2020 2:47 :32 PM Phil Sobottke-i83469 I Chemistry - Cross Discipline Review 10/21 /2020 2:57:03 PM Kyle A Gerard-s2956 I 9 Radiation Protection - Cross Discipline Review 10/21 /2020 3:40:06 PM Bruce Abbgy-iO0 1155 Qualified Technical Review 10/22/2020 8:49:42 AM Kelly J Ferneau-s252555 Approval Authority 11 /4/2020 I0:51 :36AM Signature Comments

, INDIANA MICHIGAN PMP-601 0-OSD-001 Rev. 27 Page 1 of 92 l POWER OFF-SITE DOSE CALCULATION MANUAL Information I Erik Merchant Environmental Manager Environmental Writer Document Owner Cognizant Organization TABLE OF CONTENTS 1 PURPOSE AND SCOPE ................ ........... ..................... ............................. 4 2 DEFINITIONS AND ABBREVIATIONS ..... . .................................................. 4 3 DETAILS ............. ........ .. ..... . ............... ....................... ....... . ............... ...... 6 3 .1 Calculation of Off-Site Doses .................... ................ . .............. ........ ..... 6 3.1.1 Gaseous Effluent Releases .......... .. ...................... .. ............... .. ... 6 3.1 .2 Liquid Effluent Releases .................................................... .. ... 12

3. 2 Limits of Operation and Surveillances of the Effluent Release Points ....... ...... 15 3.2.1 Radioactive Liquid Effluent Monitoring Instrumentation ................ 15 3.2 .2 Radioactive Gaseous Effluent Monitoring Instrumentation .. .. .......... 16 3.2 .3 Liquid Effluents ... ............ ............................. ............ ............ 17

a. Concentration Excluding Releases via the Turbine Room Sump (TRS) Discharge .... .... ....... ... ..... ... ... ... ... ..... .................... ..17

b. Concentration of Releases from the TRS Discharge ....... ........ ..... 18

c. Dose ... .. .. ....................... ......... ... .... .... ... .. ... ...... .. .. ... ... ..19

d. Liquid Radwaste Treatment System ....................................... 19 3.2 .4 Gaseous Effluents .... ... ..... ... ... ...... ....................... ... .... .. .... ...... 22

a. Dose Rate .. ........ .. ..................................... .. ............ ...... 22

b. Dose - Noble Gases ...... ..... ..... .... .. ..... . ... ....... ............. .... ..22

c. Dose - lodine-131, lodine-133, Tritium, and Radioactive Material in Particulate Form .......... ........ ..... ..... .... .. ... .. ... ... .. .. ....... ..23

d. Gaseous Radwaste Treatment .................. .. ..................... ..... 23 3.2.5 Radioactive Effluents - Total Dose ............................. .. ................. 26 3.3 Calculation of Alarm/Trip Setpoints ...... . ........................... .. .................. 27 3.3 .1 Liquid Monitors ........ .. ...... .. ...... ........ ................ ....... ............ 28

a. Liquid Batch Monitor Setpoint Methodology ....... . ........ .. .......... 28

b. Liquid Continuous Monitor Setpoint Methodology ........ ............. 29 3.3.2 Gaseous Monitors .... .... ... .... ............. ..... .. .. ... .. ... ... ... .. ... ..... ... .32

a. Plant Unit Vent ..... ........................ ........ .............. ............ 32

b. Waste Gas Storage Tanks ...... ....... ....... ........ ...... ..... ... ..... ... . 35

c. Containment Purge and Exhaust System ...................... .. .......... 36

d. Steam Jet Air Ejector System (SJAE) .................... .. .. ... .......... 37

e. Gland Seal Condenser Exhaust ......... ... .... .. ...... .. ....... .. .......... 37

I INDIANA j MICHIGAN PMP-6010-OSD-001 Rev. 27 Page 2 of 92 POWEii OFF-SITE DOSE CALCULATION MANUAL Information I Erik Merchant Environmental Manager Environmental Writer Document Owner Cognizant Organization 3.4 Radioactive Effluents Total Dose .............. ............................................ 38 3.5 Radiological Environmental Monitoring Program (REMP) ......................... 38 3.5.1 Purpose of the REMP ............................................................ 38 3.5.2 Conduct of the REMP ............................................................ 39 3.5.3 Annual Land Use Census ........................................................ 42 3.5.4 lnterlaboratory Comparison Program ........................................ 42 3.6 Meteorological Model ....................................................................... .43

3. 7 Reporting Requirements ... .. ............................................................... 43

3. 7.1 Annual Radiological Environmental Operating Report (ARE OR) ...... 43 3.7.2 Annual Radiological Effluent Release Report (ARERR) .................. 44 3.8 10 CFR 50.75 (g) Implementation ........................................................ 46 3.9 Reporting/Management Review ........... .............. .. ....................... ......... 47 4 FINAL CONDITIONS ............................................................................ .. 47 5 REFERENCES ........................................................................................47 SUPPLEMENTS .1 Dose Factors for Various Pathways ............................................... Pages 51 - 54 .2 Radioactive Liquid Effluent Monitoring lnstruments .................... Pages 55 - 57 .3 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements .................................... Pages 58 - 59Attachment 3.4

................................ Radioactive Gaseous Effluent Monitoring Instrumentation

........................................................................................................ Pages 60 - 62 .5 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements ............................................................. Pages 63 - 64 .6 Radioactive Liquid Waste Sampling and Analysis Program ......... Pages 65 - 66 .7 Radioactive Gaseous Waste Sampling and Analysis Program ...... Pages 67 - 68 .8 Multiple Release Point Factors for Release Points ................................. Page 69

, INDIANA MICHIGAN PMP-601 0-OSD-001 Rev. 27 Page 3 of 92 l POWl'R OFF-SITE DOSE CALCULATION MANUAL Information I Erik Merchant Environmental Manager Environmental Writer Document Owner Cognizant Organization .9 Liquid Effluent Release Systems ............................................................ Page 70 . IO Plant Liquid Effluent Parameters ............................................................ Page 71 .11 Volumetric Detection Efficiencies for Principle Gamma Emitting Radionuclides for Mirion Liquid Monitors ............................. Page 72 .12 Counting Efficiency for 1/2- DRA-300 and l/2-DRA-353 ........... Pages 73 - 74 .13 Counting Efficiency for 1-WRA-713, 2-WRA-714, 1-WRA-717, and 2-WRA-718 ......................................................................... Page 75-76 .14 Gaseous Effluent Release Systems ......................................................... Page 77 .15 Plant Gaseous Effluent Parameters ......................................................... Page 78 .16 10 Year Average of 1995-2004 Data ............................................. Pages 79 - 80 .17 Annual Evaluation of x/Q and D/Q Values For All Sectors ................. Page 81 .18 Dose Factors ................................................................................... Pages 82 - 83 .19 Radiological Environmental Monitoring Program Sample Stations, Sample Types, Sample Frequencies ................................ Pages 84 - 87 .20 Maximum Values for Lower Limits of Detections A,B - REMP ..... Pages 88 - 89 .21 Reporting Levels for Radioactivity Concentrations in Environmental Samples .......................................................................... Page 90 .22 On-Site Monitoring Location - REMP ............................. ....................... Page 91 .23 Off-Site Monitoring Locations - REMP ................................................. Page 92

Information I PMP-601 0-OSD-001 I Rev. 27 I Paoe 4 of 92 OFF-SITE DOSE CALCULATION MANUAL 1 PURPOSE AND SCOPE

• The Off-Site Dose Calculation Manual (ODCM) is the top tier document for the Radiological Environmental Monitoring Program (REMP), the Radioactive Effluent Controls Program (RECP), contains criteria pertaining to the previous Radiological Effluent Technical Specifications (RETS) as defined in NUREG-0472, and fully implements the requirements of Technical Specification 5.5.3, Radioactive Effluent Controls Program.

• The ODCM contains the methodologies and parameters to be used in the calculation of off-site doses due to radioactive liquid and gaseous effluents and in the calculation of liquid and gaseous monitoring instrumentation alarm/trip setpoints.

• The ODCM provides flow diagrams detailing the treatment path and the major components of the radioactive liquid and gaseous waste management systems.

• The ODCM presents maps of the sample locations and the meteorological model used to estimate the atmospheric dispersion and deposition parameters.

• The ODCM specifically addresses the design characteristics of the Donald C. Cook Nuclear Plant based on the flow diagrams contained on the "OP Drawings" and plant "System Description" documents.

NOTE: Revision 27 of this document concludes the transition of Radiation Monitoring System (RMS) equipment. Sections and attachments will have guidance for only the currently installed Mirian equipment. Legacy guidance has been removed.

2 DEFINITIONS AND ABBREVIATIONS Term: Meaninq:

Sor shiftly At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Dor daily At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> W or weekly At least once per 7 days Mor monthly At least once per 31 days Q or quarterly At least once per 92 days SA or semi-annually At least once per 184 days R At least once per 549 days.

S/U Prior to each reactor startup p Completed prior to each release B At least once per 24 months Samplinq evolution Process of chanqinQ filters or obtaininCJ qrab samples

Information I PMP-6010-OS0-001 I Rev. 27 I PaQe 5 of 92 OFF-SITE DOSE CALCULATION MANUAL Member(s) of All persons who are not occupationally associated with the Public plant. Does not include employees of the utility, its contractors or its vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational or other purposes not associated with the plant.

Purge/purging The controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement .

Source check The qualitative assessment of Channel response when the Channel sensor is exposed to a radioactive source .

Total Fractional Level (TFL) Total Fractional Level is defined as:

Where:

C(1l = Concentration of 1st detected nuclide C(2l = Concentration of 2nd detected nuclide L(,l = Reporting Level of 1st nuclide from Attachment 3.21, Reporting Levels for Radioactivity Concentrations in Environmental Samples.

L(2) = Reporting Level of 2nd nuclide from Attachment 3 .21, Reporting Levels for Radioactivity Concentrations in Environmental Samples.

Venting Controlled process of discharging air or gas from a confinement to maintain temperature , pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required .

Vent, used in system names, does not imply a venting process.

Information I PMP-601 0-OSD-001 I Rev. 27 I Paae 6 of 92 OFF-SITE DOSE CALCULATION MANUAL 3 DETAILS 3.1 Calculation of Off-Site Doses 3.1.1 Gaseous Effluent Releases

a. The computer program MIDAS (Meteorological Information and Dose Assessment System) performs the calculation of doses from effluent releases. The site-specific parameters associated with Ml DAS reside in the following subprograms:

• MIDER

• MIDEX

• MIDEL

• MIDEG

• MIDEN

b. The subprogram used to enter and edit gaseous release data is called MD1 EQ (EQ). The data entered in EQ can be used to calculate the accumulation of dose to individual land based receptors based on hourly meteorology and release data. The air dose from this data is calculated via the XDAIR subprogram in MIDAS. It computes air dose results for use in Reg. Guide 1.21 reports and 10 CFR 50 Appendix I calculations based on routine releases.

c. The formula used for the calculation of the air dose is generated from site specific parameters and Reg. Guide 1.109 (Eq 7):

Where:

Dy, 0 13 air = the gamma or beta air dose in mrad/yr to an individual receptor x IQ = the annual average or real time atmospheric dispersion factor over land, sec/m 3 from Attachment 3.16, 10 Year Average of 1995-2004 Data Mi = the gamma air dose factor, mrad m3 / yr µCi, from Attachment 3.18, Dose Factors Ni = the beta air dose factor, mrad m3 / yr µCi, from Attachment 3.18, Dose Factors

Information I PMP-601 0-OSD-001 I Rev. 27 I Paqe 7 of 92 OFF-SITE DOSE CALCULATION MANUAL

= the release rate of radionuclide, "i", in µCi/yr.

Quantities are determined utilizing typical concentration times volumes equations that are documented in 12-THP-601 0-RPP-601, Preparation of the Annual Radioactive Effluent Release Report.

3.17E-8 = number of years in a second (years/second).

d. The value for the ground average x IQ for each sector is calculated using equations shown below. Formula used for the calculation is generated from parameters contained in MIDAS Technical Manual, XDCALC (Eq 2).

-v/iQ= _ 2.03 *T Al Um ,

• X

• Lg I Where:

2 Lg = minimum of u 2 +He Zg 2JT or Lg= 3u ZK x = distance downwind of the source, meters. This information is found in parameter 5 of MIDEX.

um, = wind speed for ground release, (meters/second) u zg = vertical dispersion coefficient for ground release, (meters),

(Reg. Guide1.111 Fig.1)

He = building height (meters) from parameter 28 of MIDER.

(Containment Building = 49.4 meters)

Tr = terrain factor ( = 1 for Cook Nuclear Plant) because we consider all our releases to be ground level (see parameter 5 in MIDEX).

2.03 = .J2.:.-1r.:.-0.393radians(22.5°)

e. The dose due to gaseous releases, other than the air dose, is calculated by the MIDAS subprogram GASPRO. GASPRO computes the accumulation of dose to individual receptors based on hourly meteorology and release data. Calculations consider the effect of each important radionuclide for each pathway, organ, age group, distance and direction.

Information I PMP-601 0-OSD-001 I Rev. 27 I PaQe 8 of 92 OFF-SITE DOSE CALCULATION MANUAL

f. Calculations are based on the environmental pathways-to-man models in Reg. Guide 1.109. The program considers 7 pathways, 8 organs, and 4 age groups in 16 direction sectors. The distances used are taken from the MIDEG file.

g. The formulas used for the following calculations are generated from site specific parameters and Reg. Guide 1.109:

1. Total Body Plume Pathway (Eq 10)

Dose (mrem/year) = 3.17E - 8

• L ( Q;

• z!Q

• S1

• DFB;)

Where :

Sr = shielding factor that accounts for the dose reduction due to shielding provided by residential structures during occupancy (maximum exposed individual = 0. 7 per Table E-15 of Reg. Guide 1.109)

DFBi = the whole body dose factor from Table B-1 of Reg.

Guide 1.109, mrem - m3 per µCi - yr. See Attachment 3.18, Dose Factors .

Qi = the release rate of radionuclide "i", in µCi/yr

2. Skin Plume Pathway (Eq 11)

Dose(mrem/yr)= 3.17E-8* 1 * ~ * [L(Q;

• 1.11* DFT )+ L(Q;

• DFS;)}

s Where:

1.11 = conversion factor, tissue to air, mrem/mrad OF i Y = the gamma air dose factor for a uniform semi-infinite cloud of radionuclide "i", in mrad m 3/µCi yr from Table B-1, Reg. Guide 1.109. See Attachment 3.18, Dose Factors.

DFSi = the beta skin dose factor for a semi-infinite cloud of radionuclide "i", in mrem m3/µCi yr from Table B-1, Reg. Guide 1.109. See Attachment 3.18, Dose Factors.

Information I PMP-601 0-OSD-001 I Rev. 27 I Paae 9 of 92 OFF-SITE DOSE CALCULATION MANUAL

3. Radionuclide and Radioactive Particulate Doses (Eq 13 & 14)

The dose, D 1p in mrem/yr, to an individual from radionuclides, other than noble gases, with half-lives greater than eight days in gaseous effluents released to unrestricted areas will be determined as follows:

DiP (mrem/year) = 3.17E - 8

• L( R;

• W

• Q;)

Where:

Ri = the most restrictive dose factor for each identified radionuclide "i", in m 2 mrem sec/ yr µCi (for food and ground pathways) or mrem m 3 / yr µCi (for inhalation pathway), for the appropriate pathway For sectors with existing pathways within five miles of the site, use the values of Ri for these real pathways, otherwise use pathways distance of five miles. See Attachment 3.1, Dose Factors for Various Pathways, for the maximum Ri values for the most controlling age group for selected radionuclides. Ri values were generated by computer code PARTS, see NUREG-0133, Appendix D.

W = the annual average or real time atmospheric dispersion parameters for estimating doses to an individual at the worst case location, and where W is further defined as:

Win = x IQ for the inhalation pathway, in sec/m 3

-OR-Wr9 = DIQ for the food and ground pathways in 1/m2 Oic = the release rate of those radioiodines, radioactive materials in particulate form and radionuclides other than noble gases with half-lives greater than eight days, in µCi/yr

h. This calculation is made for each pathway. The maximum computed dose at any receptor for each pathway is selected. These are summed together to get the dose to compare to the limits. Only the maximum of the cow milk or goat milk pathway (not both) is included in the total.

Information I PMP-601 0-OSD-001 I Rev. 27 I Page 10 of 92 OFF-SITE DOSE CALCULATION MANUAL

i. In addition to the above routines, the QUICKG routine of the MIDAS system may be used to provide data used in the monthly reports due to its ability to use annual average meteorological data rather than real time data, thus shortening the run time involved.

j. Carbon-14 (C-14) supplemental information

1. The quantity of C-14 released to the environment may be estimated by use of a C-14 source term scaling factor based on power generation (Ref. RG 1.21, Revision 2). A recent study recommends a source term scaling factor of approximately 9.0 to 9.8 Curies/GWe-yr for a Westinghouse Pressurized Water Reactor (Ref.

EPRI 1021106 "Estimation of Carbon-14 in Nuclear Plant Gaseous Effluents" December 23, 2010). For this method, a scaling factor of 9.4 Curies/GWe-yr shall be used.

2. C-14 releases from PWRs occur primarily as a mix of organic carbon (methane) and inorganic carbon (carbon dioxide). For this method, an average organic fraction of 80% with the remaining 20% being assumed as carbon dioxide shall be used.

3. Dose is calculated utilizing the methodology prescribed in RG 1.109 Appendix C, with the vegetation dose being the most predominant.

Aqjustments for growing seasons, percentage of C-14 generated assumed released from the reactor coolant in gaseous form via batch releases, seasonal X I Q , and other industry methodologies being considered by the NRC may be applied as desired should their acceptance of these methods occur.

k. Steam Generator Slowdown System (Start Up Flash Tank Vent)

1. The amount of radioiodine and other radionuclides that are released via the startup flash tank and its vent are calculated through actual sample results while the startup flash tank is in service.

2. The following calculation is performed to determine the amount of curies released through this pathway. (Plant established formula.)

Curies= µCi* GPM

• time on flash tank (min)* 3. 785E - 3 ml Where: 3. 785E-3 = conversion factor, ml Ci/µCi gal.

3. The flow rate is determined from the blowdown valve position and the time on the startup flash tank, or using installed plant blowdown flow instrumentation. Chemistry Department performs the sampling and analysis of the samples.

Information I PMP-6010-OSD-001 I Rev. 27 I PaQe 11 of 92 OFF-SITE DOSE CALCULATION MANUAL

4. This data is provided to the MIDAS computer and dose calculations (liquid and gas) are performed to ensure compliance with Subsection 3.2, Limits of Operation and Surveillances of the Effluent Release Points, dose limits. MIDAS uses the formulas given in step 3.1.2, Liquid Effluent Releases, to calculate doses to members of the public.

NOTE: This section provides the minimum requirements to be followed at Donald C.

Cook Nuclear Plant. This would be used if actual sample data was not available each time the startup flash tank was in service.

5. The radioiodine release rate must be determined in accordance with the following equation every 31 day period whenever the specific activity of the secondary coolant system is greater than 0.01 µCi/g dose equivalent 1-131.

6. IF the specific activity of the secondary coolant system is less than 0.01 µCi/g dose equivalent 1-131, THEN the release rate must be determined once every six months. Use the following plant established equation:

Qy =Ci* JPF* Rsgb Where:

Oy = the release rate of 1-131 from the steam generator flash tank vent, in µCi/sec Ci = the concentration (µCi/cc) of 1-131 in the secondary coolant averaged over a period not exceeding seven days IPF = the iodine partition factor for the Start Up Flash Tank, 0.05, in accordance with NUREG-0017 Rsgb = the steam generator blowdown rate to the startup flash tank, in cc/sec

7. Use the calculated release rate in monthly dose projections until the next determination to ensure compliance with Subsection 3.2, Limits of Operation and Surveillances of the Effluent Release Points, dose limits. Report the release rate calculations in the Annual Radioactive Effluent Release Report.

Information I PMP-6010-OSD-001 I Rev. 27 I Page 12 of 92 OFF-SITE DOSE CALCULATION MANUAL 3.1.2 Liquid Effluent Releases

a. The calculation of doses from liquid effluent releases is also performed by the MIDAS program. The subprogram used to enter and edit liquid release data is called MD1 EB (EB).

b. To calculate the individual dose (mrem), the program DS1 LI (LD) is used. It computes the individual dose for up to 5 receptors for 14 liquid pathways due to release of radioactive liquid effluents. The pathways can be selected using the MIDEL program and changing the values in parameter 1. D.C. Cook Nuclear Plant uses 3 pathways: potable water, shoreline, and aquatic foods (fresh water sport fishing).

c. Steam Generators are typically sparged, sampled, and drained as batches usually early in outages to facilitate cooldown for entry into the steam generator. This is also typically repeated prior to startup to improve steam generator chemistry for the startup. The sample stream, if being routed to the operating unit blowdown, is classified as a continuous release for quantification purposes to maintain uniformity with this defined pathway.

d. The equations used are generated from site specific data and Reg. Guide 1.109. They are as follows:

1. Potable Water (Eq 1)

R =1100* Uap *'°'Q

• D. * -;.,,,

• Pl M p* F* 2.23£-3 ~ ; a,p,e Where:

RapJ = the total annual dose to organ ':_j" to individuals of age groups "a" from all of the nuclides "i" in pathway "p",

in mrem/year 1100 = conversion factor, yr ft3 pCi / Ci sec L Uap = a usage factor that specifies the exposure time or intake rate for an individual of age group "a" associated with pathway "p". Given in #29-84 of parameter 4 in MIDEL and Reg. Guide 1.109 Table E-5. See Attachment 3 .1, Dose Factors for Various Pathways.

Mp = the dilution factor at the point of exposure (or the point of withdrawal of drinking water or point of harvest of aquatic food). Given in parameter 5 of MIDEL as 2.6.

Information I PMP-601 0-OSD-001 I Rev. 27 I Page 13 of 92 OFF-SITE DOSE CALCULATION MANUAL F = the circulation water system water flow rate, in gpm, is used for evaluating dose via these pathways as dilution flow 2.23E-3 = conversion factor, ft 3 min/ sec gal Qi = the release rate of nuclide "i" for the time period of the run input via MIDEB, Curies/year Daipj = the dose factor, specific to a given age group "a",

radionuclide "i", pathway "p", and organ 'T', which can be used to calculate the radiation dose from an intake of a radionuclide, in mrem/pCi. These values are taken from tables E-11 through E-14 of Reg. Guide 1.109 and are located within the MIDAS code.

Ai = the radioactive decay constant for radionuclide "i", in hours*1 tp = the average transit time required for nuclides to reach the point of exposure, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. This allows for nuclide transport through the water purification plant and the water distribution system. For internal dose, tp is the total elapsed time between release of the nuclides and ingestion of food or water, in hours. Given as #25 of parameter 4 in MIDEL. (tp = 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)

2. Aquatic Foods (Eq 2)

Rap)

=1100* Uap Mp*F*2.23E-3 "'7

• B*

• D awe

• '°'Q i 'P

• • -).,ip Where:

Bip = the equilibrium bioaccumulation factor for nuclide "i" in pathway "p", expressed as pCi L / kg pCi. The factors are located within the Ml DAS code and are taken from TableA-1 of Reg. Guide1.109. SeeAttachment3.1, Dose Factors for Various Pathways.

tp = the average transit time required for nuclides to reach the point of exposure, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This allows for decay during transit through the food chain, as well as during food preparation. Given as #26 of parameter 4 in MIDEL. (tp = 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />)

Mp = the dilution factor at the point of exposure, 1.0 for Aquatic Foods. Given in parameter 5 of MIDEL as 1.0.

Information I PMP-6010-OSD-001 I Rev. 27 I Page 14 of 92 OFF-SITE DOSE CALCULATION MANUAL

3. Shoreline Deposits (Eq 3)

R ap;. = 110' 000

• MP* Uap *W *

• D a,p;.. [e-).;tp]* [1-e-).;tb]

• ""'Q* T1 F

• 2.23£-3 ~ 1 Where:

W = the shoreline width factor. Given as an input of 0.3 when running the program, based on Table A-2 in Reg.

Guide 1.109.

Ti = the radioactive half-life of the nuclide, "i ", in days Daipj = the dose factor for standing on contaminated ground, in mrem m2 / hr pCi. The values are taken from table E-6 of Reg. Guide 1.109 and are located within the MIDAS code.

See Attachment 3.1, Dose Factors for Various Pathways.

tb = the period of time for which sediment or soil is exposed to the contaminated water, 1.31 E + 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. Given in MIDEL as item 6 of parameter 4.

tp = the average transit time required for nuclides to reach the point of exposure, 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> . Given as #28 of parameter 4 in MIDEL.

110,000 = conversion factor yr ft3 pCi / Ci sec m2 day, this accounts for proportionality constant in the sediment radioactivity model Mp = the dilution factor at the point of exposure (or the point of withdrawal of drinking water or point of harvest of aquatic food). Given in parameter 5 of MIDEL as 2.6.

e. The MIDAS program uses the following plant specific parameters, which are entered by the operator .

1. Irrigation rate = 0

2. Fraction of time on pasture = 0

3. Fraction of feed on pasture = 0

4. Shore width factor = 0.3 (from Reg . Guide 1.109, Table A-2)

f. The results of DS1 LI are printed in LDRPT {LP). These results are used in the monthly report of liquid releases.

Information I PMP-601 0-OSD-001 I Rev. 27 I Paqe 15 of 92 OFF-SITE DOSE CALCULATION MANUAL

g. In addition, the program DOSUM (DM) is used to search the results files of DS1 LI to find the maximum liquid pathway individual doses. The highest exposures are then printed in a summary table. Each line is compared with the appropriate dose limit. The table provides a concise summary of off-site environmental dose calculations for inclusion in Annual Radioactive Effluent Release Reports, required by Reg. Guide 1.21.

NOTE: The performance of each surveillance requirement must be within the specified time interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

3.2 Limits of Operation and Surveillances of the Effluent Release Points 3.2.1 Radioactive Liquid Effluent Monitoring Instrumentation

a. The radioactive liquid effluent monitoring instrumentation channels shown in Attachment 3.2, Radioactive Liquid Effluent Monitoring Instruments, are operable with their alarm/trip setpoints set to ensure that the limits of step 3.2.3a, Concentration Excluding Releases via the Turbine Room Sump (TRS) Discharge, are not exceeded.

b. The applicability of each channel is shown in Attachment 3.2, Radioactive Liquid Effluent Monitoring Instruments.

c. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than a value which will ensure the limits of step 3.2.3a, Concentration Excluding Releases via the Turbine Room Sump (TRS) Discharge, are met without delay, suspend the release of radioactive liquid effluents monitored by the affected channel and reset or declare the monitor inoperable.

d. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels operable, take the applicable action shown in Attachment 3.2, Radioactive Liquid Effluent Monitoring Instruments, with a maximum allowable extension not to exceed 25% of the surveillance interval, excluding the initial performance.

e. Determine the setpoints in accordance with the methodology described in step 3.3.1, Liquid Monitors. Record the setpoints.

Information I PMP-601 0-OSD-001 I Rev. 27 I Paqe 16 of 92 OFF-SITE DOSE CALCULATION MANUAL

f. Demonstrate each radioactive liquid effluent monitoring instrumentation channel is operable by performing the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL OPERATIONAL TEST at the frequencies shown in Attachment 3.3, Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements.

BASES - LIQUID The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria specified in Section 11.3 of the Final Safety Analysis Report for the Donald C. Cook Nuclear Plant.

Due to the location of the ESW monitors, outlet line of containment spray heat exchanger (typically out of service), weekly sampling is required of the ESW system for radioactivity.

This is necessary to ensure monitoring of a CCW to ESW system leak. [Ref 5.2.1hh]

3.2.2 Radioactive Gaseous Effluent Monitoring Instrumentation

a. The radioactive gaseous process and effluent monitoring instrumentation channels shown in Attachment 3.4, Radioactive Gaseous Effluent Monitoring Instrumentation, are operable with their alarm/trip setpoints set to ensure that the limits of step 3.2.4a, Dose Rate, are not exceeded.

b. The applicability of each channel is shown in Attachment 3.4, Radioactive Gaseous Effluent Monitoring Instrumentation.

c. With a radioactive gaseous process or effluent monitoring instrumentation channel alarm/trip setpoint less conservative than a value which will ensure that the limits of step 3.2.4a, Dose Rate, are met, without delay, suspend the release of radioactive gaseous effluents monitored by the affected channel and reset or declare the channel inoperable.

Information I PMP-601 0-OSD-001 I Rev. 27 I Page 17 of 92 OFF-SITE DOSE CALCULATION MANUAL

d. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels operable, take the action shown in Attachment 3.4, Radioactive Gaseous Effluent Monitoring Instrumentation, with a maximum allowable extension not to exceed 25% of the surveillance interval, excluding the initial performance.

NOTE: This surveillance requirement does not apply to the waste gas holdup system hydrogen and oxygen monitors, as their setpoints are not addressed in this document.

e. Determine the setpoints in accordance with the methodology as described in step 3.3.2, Gaseous Monitors. Record the setpoints.

f. Demonstrate each radioactive gaseous process or effluent monitoring instrumentation channel is operable by performing the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL OPERATIONAL TEST operations at the frequencies shown in Attachment 3.5, Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements.

BASES - GASEOUS The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases. The alarm/trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure the alarm/trip will occur prior to exceeding the limits of 10 CFR Part 20 . The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria specified in Section 11.3 of the Final Safety Analysis Report for the Donald C. Cook Nuclear Plant.

3.2.3 Liquid Effluents

a. Concentration Excluding Releases via the Turbine Room Sump (TRS)

Discharge

1. Limit the concentration of radioactive material released via the Batch Release Tanks or Plant Continuous Releases (excluding only TRS discharge to the Absorption Pond) to unrestricted areas to the concentrations in 10 CFR 20, Appendix B, Table 2, Column 2, for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, limit the concentration to 2E-4 µCi/ml total activity.

Information I PMP-601 0-OSD-001 I Rev. 27 I Paqe 18 of 92 OFF-SITE DOSE CALCULATION MANUAL

2. With the concentration of radioactive material released from the site via the Batch Release Tanks or Plant Continuous Releases (other than the TRS to the Absorption Pond) exceeding the above limits, without delay restore the concentration to within the above limits.

3. Sample and analyze radioactive liquid wastes according to the sampling and analysis program of Attachment 3.6, Radioactive Liquid Waste Sampling and Analysis Program.

4. Use the results of radioactive analysis in accordance with the methods of this document to assure that all concentrations at the point of release are maintained within limits.

b. Concentration of Releases from the TRS Discharge

1. Limit releases via the TRS discharge to the on-site Absorption Pond to the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2. For dissolved or entrained noble gases, limit the concentration to 2E-4 µCi/ml total activity.

2. With releases from the TRS exceeding the above limits, perform a dose projection due to liquid releases to UNRESTRICTED AREAS to determine if the limits of step 3.2.3c.1 have been exceeded. If the dose limits have been exceeded, follow the directions in step 3.2.3c.2, as applicable.

3. Sample and analyze radioactive liquid wastes according to the program in Attachment 3.6, Radioactive Liquid Waste Sampling and Analysis Program.

4. Use the results of radioactive analysis in accordance with the methods of this document to assure that all concentrations at the point of release are maintained within the limits stated above.

Information I PMP-601 0-OSD-001 I Rev. 27 I Page 19 of 92 OFF-SITE DOSE CALCULATION MANUAL

c. Dose

1. Limit the dose or dose commitment to an individual from radioactive material in liquid effluents released to unrestricted areas during any calendar quarter to~ 1.5 mrem/unit to the total body and to~ 5 mrem/unit to any organ, and during any calendar year to~ 3 mrem/unit to the total body and to~ 10 mrem/unit to any organ.

2. With the calculated release of radioactive materials in liquid effluents exceeding ten times any of the limits in Steps 3.2.3a or 3.2.3b, or exceeding 3.2.3c.1 above, prepare and submit a Written Report, pursuant to 10 CFR 20.2203, within 30 days after learning of the event. This report must describe the extent of exposure of individuals to radiation and radioactive material, including, as appropriate:

a) Estimate of each individual's dose. This is to include the radiological impacts on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act (applicable due to Lake Township water treatment facility),

b) Levels of radiation and concentration of radioactive material involved, c) Cause of elevated exposures, dose rates or concentrations,

-AND-d) Corrective steps taken or planned to ensure against recurrence, including schedule for achieving conformance with applicable limits.

These reports must be formatted in accordance with PMP-7030-001-002, Licensee Event Reports, Special and Routine Reports, even though this is not an LER.

3. Determine cumulative and projected dose contributions from liquid effluents in accordance with this document at least once per 31 days.

Dose may be prajected based on estimates from previous monthly projections and current or future plant conditions.

d. Liquid Radwaste Treatment System

1. Use the liquid radwaste treatment system to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the site when averaged over 31 days, would exceed 0.12 mrem (0.06 mrem/unit x 2 units) to the total body or 0.4 mrem (0.2 mrem/unit x 2 units) to any organ.

2. Project doses due to liquid releases to UNRESTRICTED AREAS at least once per 31 days, in accordance with this document.

Information I PMP-601 0-OSD-001 I Rev. 27 I PaQe 20 of 92 OFF-SITE DOSE CALCULATION MANUAL

e. During times of primary to secondary leakage, the use of the startup flash tank should be minimized to reduce the release of curies from the secondary system and to maintain the dose to the public ALARA.

Drainage of high conductivity water (Component Cooling Water and ice melt water containing sodium tetraborate) shall be evaluated to decide whether it should be drained to waste (small volumes only), the Turbine Room Sump (low activity water only) or routed without demineralization processing to a monitor tank for release. This is necessary in order to minimize the detrimental effect that high conductivity water has on the radioactive wastewater demineralization system. The standard concentration and volume equation can be utilized to determine the impact on each method and is given here. The units for concentration and volume need to be consistent across the equation:

( C;) ( II;) + ( Ca) ( Va) = (Cr) ( l-'t)

Where:

Ci = the initial concentration of the system being added to vi = the initial volume of the system being added to Ca = the concentration of the water that is being added to the system Va = the volume of the water that is being added to the system Ct = the final concentration of the system after the addition Vt = the final volume of the system after the addition The intent is to keep the:

• WDS below 500 µmhos/cc.

• TRS below lE-5 µC/cc.

• Monitor Tank release ALARA to members of the public.

Wastewater leakage into the liquid waste disposal system will be monitored routinely. In the event the leak rate is determined to be over two gallons per minute (the assumed plant design leakage based on the original 2 gpm waste evaporator), increased scrutiny will be placed on locating in-leakage, timeliness of job order activities, and/or activities causing increased production of waste water.

Information I PMP-601 0-OSD-001 I Rev . 27 I Page 21 of 92 OFF-SITE DOSE CALCULATION MANUAL BASES - CONCENTRATION This specification is provided to ensure the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20, Appendix B, Table 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposures greater than 1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to an individual and 2) the limits of 10 CFR Part 20. The concentration I imit for noble gasses is based upon the assumption that Xe-135 is the controlling radionuclide and its Effluent Concentration Unit in air (submersion) was converted to an equivalent concentration in water using the methods described in the International Commission on Radiological Protection (ICRP) Publication 2.

DOSE This specification is provided to implement the requirements of Sections I I .A, III.A, and IV.A of Appendix I, 10 CFR Part 50 . The dose limits implement the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time, implement the guides set forth in Section IV.A of Appendix I to assure the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable". Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in the ODCM implement the requirements in Section 111. A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents, will be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977, and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases forthe Purpose of Implementing Appendix I", April 1977. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guide 1.109 and 1.113.

This specification applies to the release of liquid effluents from each reactor at the site. The liquid effluents from the shared system are proportioned among the units sharing the system.

Information I PMP-601 0-OSD-001 I Rev. 27 I Paqe 22 of 92 OFF-SITE DOSE CALCULATION MANUAL LIQUID WASTE TREATMENT The operability of the liquid radwaste treatment system ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirements that the appropriate portions of this system be used when specified provide assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This specification implements the requirements of 10 CFR Part 50.36a, General Design Criteria Section 11.1 of the Final Safety Analysis Report for the Donald C. Cook Nuclear Plant, and design ol:!jective Section I1.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable fraction of the dose design objectives set forth in Section I I .A of Appendix I, 10 CFR Part 50, for liquid effluents .

3.2 .4 Gaseous Effluents

a. Dose Rate

1. Limit the dose rate due to radioactive materials released in gaseous effluents from the site to :s; 500 mrem/yr to the total body and

s; 3000 mrem/yr to the skin for noble gases . Limit the dose rate due to all radioiodines and for all radioactive materials in particulate form and radionuclides (other than noble gases) with half-lives greater than eight days to :s; 1500 mrem/yr to any organ .

2. With the dose rate(s) exceeding the above limits, without delay decrease the release rate to within the above limit(s) .

3. Determine the dose rate due to noble gases in gaseous effluents to be within the above limits in accordance with the methods and procedures described in this document.

4. Determine the dose rate due to radioactive materials, other than noble gases, in gaseous effluents to be within the above limits in accordance with the methods and procedures of this document by obtaining representative samples and performing analyses in accordance with the sampling and analysis program in Attachment 3.7, Radioactive Gaseous Waste Sampling and Analysis Program.

b. Dose - Noble Gases

1. Limit the air dose in unrestricted areas due to noble gases released in gaseous effluents during any calendar quarter, to :s; 5 mrad/unit for gamma radiation and :s; 10 mrad/unit for beta radiation and during any calendar year, to :s; 10 mrad/unit for gamma radiation and :s; 20 mrad/unit for beta radiation.

Information I PMP-601 0-OSD-001 I Rev. 27 I Page 23 of 92 OFF-SITE DOSE CALCULATION MANUAL

2. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit a Written Report, pursuant to 10 CFR 20.2203 and addressed in step 3.2.3c.2, within 30 days after learning of the event.

3. Determine cumulative and prqjected dose contributions for the total time period in accordance with this document at least once every 31 days.

c. Dose - lodine-131, lodine-133, Tritium, and Radioactive Material in Particulate Form

1. Limit the dose to a MEMBER OF THE PUBLIC from radioiodine, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than eight days in gaseous effluents released to unrestricted areas (site boundary) to the following:

a) During any calendar quarter to less than or equal to 7 .5 mrem/unit to any organ b) During any calendar year to less than or equal to 15 mrem/unit to any organ.

2. With the calculated dose from the release of radioiodines, radioactive materials in particulate form, or radionuclides other than noble gases in gaseous effluents exceeding any of the above limits, prepare and submit a Written Report, pursuant to 10 CFR 20.2203 and addressed in step 3.2.3c.2, within 30 days after learning of the event.

3. Determine cumulative and prqjected dose contributions for the total time period in accordance with this document at least once every 31 days.

d. Gaseous Radwaste Treatment

1. The UFSAR (Updated Final Safety Analysis Report) states that radioactive waste gas should be held for 45 days of decay time.

2. Use the gaseous radwaste treatment system and the ventilation exhaust treatment system to reduce radioactive materials in gaseous wastes prior to their discharge when projected gaseous effluent air doses due to gaseous effluent releases to unrestricted areas when averaged over 31 days, would exceed 0.4 mrad (0.2 mrad/unit x 2 units) for gamma radiation and 0.8 mrad (0.4 mrad/unit x 2 units) for beta radiation.

Use the ventilation exhaust treatment system to reduce radioactive materials in gaseous waste prior to their discharge when the prqjected doses due to gaseous effluent releases to unrestricted areas when averaged over 31 days would exceed 0.3 mrem/unit to any organ .

Information I PMP-601 0-OSD-001 I Rev. 27 I Page 24 of 92 OFF-SITE DOSE CALCULATION MANUAL

3. Project doses due to gaseous releases to UNRESTRICTED AREAS at least once per 31 days in accordance with this document.

BASES -- GASEOUS EFFLUENTS This specification provides reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a Member of the Public in an unrestricted area, either at or beyond the site boundary in excess of the design objectives of appendix I to 10 CFR 50. This specification is provided to ensure that gaseous effluents from all units on the site will be appropriately controlled. It provides operational flexibility for releasing gaseous effluents to satisfy the Section II.A and I1.C design objectives of appendix I to 10 CFR 50.

For individuals who may at times be within the site boundary, the occupancy of the individual will be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the site boundary. The specified instantaneous release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the site boundary to::;; 500 mrem/yr to the total body or to::;; 3000 mrem/yr to the skin.

These instantaneous release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to::;; 1500 mrem/yr. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary conforming to the doses associated with 10 CFR 20, Appendix B, Table 2, Column 1.

This specification applies to the release of gaseous effluents from all reactors at the site. The gaseous effluents from the shared system are proportioned among the units sharing that system.

DOSE, NOBLE GASES This specification is provided to implement the requirements of Sections 11.B, Ill.A, and IV.A of Appendix I, 10 CFR Part 50. The dose limits implement the guides set forth in Section I1.B of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable".

The Surveillance Requirements implement the requirements in Section I I I.A of Appendix I that conform with the guides of Appendix I to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated . The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents will be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors",

Revision 1, July 1977. The ODCM equations provided for determining the air doses at the site boundary will be based upon the historical average atmospherical conditions. NUREG-0133 provides methods for dose calculations consistent with Regulatory Guides 1.109 and 1.111.

Information I PMP-601 0-OSD-001 I Rev. 27 I Page 25 of 92 OFF-SITE DOSE CALCULATION MANUAL DOSE, RADIOIODINES, RADIOACTIVE MATERIAL IN PARTICULATE FORM, AND RADIONUCLIDES OTHER THAN NOBLE GASES This specification is provided to implement the requirements of Sections 11.C, Ill.A, and IV.A of Appendix I, 10 CFR Part 50. The dose limits are the guides set forth in Section I1.C of Appendix I.

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable".

The ODCM calculational methods specified in the surveillance requirements implement the requirements in Section II I.A of Appendix I that conform with the guides of Appendix I to be shown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially underestimated.

The ODCM calculational methods approved by the NRC for calculating the doses due to the actual release rates of the subject materials are required to be consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors", Revision 1, July 1977 . These equations also provide the methodology for determining the actual doses based upon the historical average atmospheric conditions. The release rate specifications for radioiodines, radioactive material in particulate form, and radionuclides, other than noble gases, are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which are examined in the development of these calculations are: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man,

3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

GASEOUS WASTE TREATMENT The operability of the gaseous radwaste treatment system and the ventilation exhaust treatment systems ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used when specified provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable".

This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion Section 11.1 of the Final Safety Analysis Report for the Donald C. Cook Nuclear Plant, and design objective Section I1.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the guides forth in Sections 11.B and I1.C of Appendix I, 10 CFR Part 50, for gaseous effluents.

Information I PMP-601 0-OSD-001 I Rev. 27 I Paqe 26 of 92 OFF-SITE DOSE CALCULATION MANUAL 3.2.5 Radioactive Effluents - Total Dose

a. The dose or dose commitment to a real individual from all uranium fuel cycle sources is limited to ::5: 25 mrem to the total body or any organ (except the thyroid, which is limited to ::5: 75 mrem) over a period of 12 consecutive months.

b. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of steps 3.2.3c (Dose), 3.2.4b (Dose - Noble Gases), or 3.2.4c (Dose - lodine-131, lodine-133, Tritium, and Radioactive Material in Particulate Form) during any calendar quarter, perform the following:

• Investigate and identify the causes for such release rates;

• Define and initiate a program for corrective action;

• Report these actions to the NRC within 30 days from the end of the quarter during which the release occurred.

IF the estimated dose(s) exceeds the limits above, and IF the release condition resulting in violation has not already been corrected prior to violation of 40 CFR 190, THEN include in the report a request for a variance in accordance with the provisions of 40 CFR 190 and including the specified information of paragraph 190.11 (b). Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete. The variance only relates to the limits of 40 CFR 190, and does not apply in any way to the requirements for dose limitation of 10 CFR 50, as addressed in other sections of this document.

c. Determine cumulative dose contributions from liquid and gaseous effluents in accordance with this document (including steps 3.2.3c

[Dose], 3.2.4b [Dose - Noble Gases], or 3.2.4c [Dose - lodine-131, lodine-133, Tritium, and Radioactive Material in Particulate Form]).

Information I PMP-601 0-OSD-001 I Rev. 27 I PaQe 27 of 92 OFF-SITE DOSE CALCULATION MANUAL BASES -- TOT AL DOSE This specification is provided to meet the dose limitations of 40 CFR 190. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant radioactive effluents exceed twice the design objective doses of Appendix I. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a member of the public will exceed the dose limits of 40 CFR 190 if the individual reactors remain within the reporting requirement level. The Special Report will describe a course of action, which should result in the limitations of dose to a member of the public for 12 consecutive months to within the 40 CFR 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to any member of the public from other uranium fuel cycle sources is negligible with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 5 miles must be considered. If the dose to any member of the public is estimated to exceed the requirements of 40 CFR 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR 190 have not already been corrected, in accordance with the provision of 40 CFR 190.11), is considered to be a timely request and fulfills the requirements of 40 CFR 190 until NRC staff action is completed.

An individual is not considered a member of the public during any period in which he/she is engaged in carrying out any operation, which is part of the nuclear fuel cycle.

3.3 Calculation of Alarm/Trip Setpoints The alarm and trip setpoints are to provide monitoring, indication, and control of liquid and gaseous effluents. The setpoints are used in conjunction with sampling programs to assure that the releases are kept within the limits of 10 CFR 20, Appendix B, Table 2.

Establish setpoints for liquid and gaseous monitors. Depending on the monitor function, it would be a continuous or batch monitor. The different types of monitors are suqject to different setpoint methodologies.

One variable used in setpoint calculations is the multiple release point (MRP) factor.

The MRP is a factor used such that when all the releases are integrated, the applicable LIMIT value will not be exceeded. The MRP is determined such that the sum of the MRP's for that effluent type (liquid or gaseous) is less than or equal to 1. The value of the MRP is arbitrary, and it should be assigned based on operational performance. The values of the MRP's for each liquid release point are given in Attachment 3.8, Multiple Release Point Factors for Release Points.

The Site stance on instrument uncertainty is taken from HPPOS-223, Consideration of Measurement Uncertainty When Measuring Radiation Levels Approaching Regulatory Limits, which states the NRC position is the result of a valid measurement obtained by a method, which provides a reasonable demonstration of compliance. This value should be accepted and the uncertainty in that measured value need not be considered.

Information I PMP-601 0-OSD-001 I Rev . 27 I Paqe 28 of 92 OFF-SITE DOSE CALCULATION MANUAL 3.3.1 Liquid Monitors Establish liquid monitor setpoints for each monitor of the liquid effluent release systems. A schematic of the liquid effluent release systems is shown as Attachment 3.9, Liquid Effluent Release Systems. A list of the Plant Liquid Effluent Parameters is in Attachment 3.10, Plant Liquid Effluent Parameters.

The details of each system design and operation can be found in the system descriptions. The setpoints are intended to keep releases within the limits of 10 CFR 20, Appendix B, Table 2, Column 2. Determine setpoints using either the batch or the continuous methodology.

NOTE: The naming of specific monitors and detectors may vary due to software limitations requiring the usage of an approved acronym or alias to compensate for this inability of the software to accept the actual plant component label on redundant equipment. RRS-1001 is an example where the RRS-1001-B has a software alias of RRS-1021-B and either label is correct. The OPS procedures utilize the RRS-1021-B naming and this will be reflected throughout the ODCM.

a. Liquid Batch Monitor Setpoint Methodology

1. There are two monitors used on the Waste Disposal System for liquid batch releases. These monitors are identified as RRS-1001-A [primary]

and RRS-1021-B [back-up]. Steam Generator Slowdown radiation monitors also can be used to monitor batch releases while draining steam generators. The function of these monitors is to act as a check on the sampling program. The sampling program determines the nuclides and concentrations of those nuclides prior to release. The discharge and dilution flow rates are then adjusted to keep the release within the limits of 10 CFR 20. Based on the concentrations of nuclides in the release, the count rate on the monitor can be predicted. The high alarm setpoint can then be set above the predicted value up to the maximum setpoint of the system.

2. The radioactive concentration of each batch of radioactive liquid waste to be discharged is determined prior to each release by sampling and analysis in accordance with Attachment 3.6, Radioactive Liquid Waste Sampling and Analysis Program.

3. The allowable release flow rates are determined in order to keep the release concentrations within the requirements of 10 CFR 20, Appendix B, Table 2, Column 2. The equation to calculate the flow rate is from Addendum AA 1 of NUREG-0133:

Information I PMP-601 0-OSD-001 I Rev. 27 I Page 29 of 92 OFF-SITE DOSE CALCULATION MANUAL L C; ]*_j_<.5.F+ f

[ LIMIT; MRP Where:

Ci = the concentration of nuclide "i" in µCi/ml LIMITi = the 10 CFR 20, Appendix B, Table 2, Column 2 limit of nuclide "i" in µCi/ml f = the effluent flow rate in gpm (Attachment 3.10, Plant Liquid Effluent Parameters)

F = the dilution water flow rate as estimated prior to release.

The dilution flow rate is a multiple of 230,000 gpm depending on the number of circulation pumps in operation.

MRP = the multiple release point factor. A factor such that when all the release points are operating at one time the limits of 10 CFR 20 will not be exceeded.

4. This equation must be true during the batch release. Before the release is started, substitute the maximum effluent flow rate and the minimum dilution flow rate for f and F, respectively. If the equation is true, the release can proceed with those flow rates as the limits of operation. If the equation is not true, the effluent flow rate can be reduced or the dilution flow rate can be increased to make the equation true. This equation may be rearranged to solve for the maximum effluent release flow rate (f).

5. The setpoint is used as a quality check on the sampling program.

The setpoint is used to stop the effluent flow when the monitor reading is significantly greater than the predicted value from the sampling program. The predicted value is generated by converting the effluent concentration for each gamma emitting radionuclide to counts per unit of time as per Attachment 3.11, Volumetric Detection Efficiencies for Principle Gamma Emitting Radionuclides for Mirion Liquid Monitors, or Attachment 3 .12, Counting Efficiency for 1/2-DRA-300 and l/2-DRA-353. The sum of all the counts per unit of time is the predicted count rate. The predicted count rate can then be multiplied by a factor and combined with the background counts to determine the high alarm setpoint that will provide a high degree of conservatism and eliminate spurious alarms.

Information I PMP-601 0-OSD-001 I Rev. 27 I Page 30 of 92 OFF-SITE DOSE CALCULATION MANUAL

b. Liquid Continuous Monitor Setpoint Methodology

1. There are eight monitors used as potential continuous liquid release monitors. These monitors are used in the steam generator blowdown (SGBD), blowdown treatment (BOT), and essential service water (ESW) systems.

2. These Mirian monitors are identified as:

• 1/2-DRA-300 for SGBD

• 1/2-DRA-353 for BOT

• Unit 1: WRA-713, WRA-717 and Unit 2: WRA-714, WRA-718 for ESW The function of these monitors is to assure that releases are kept within the concentration limits of 10 CFR 20, Appendix B, Table 2, Column 2, entering the unrestricted area following dilution.

3. The monitors on steam generator blowdown and blowdown treatment systems have trip functions associated with their setpoints.

Essential service water monitors are equipped with an alarm function only and monitor effluent in the event the Containment Spray Heat Exchangers are used.

4. The equation used to determine the setpoint for continuous monitors is from Addendum AA1 of NUREG-0133:

C* Eff* MRP* F*SF Sp~ f Where:

Sp = setpoint of monitor (cpm)

C = SE-7 µCi/ml, maximum effluent control limit from 10 CFR 20, Appendix B, Table 2, Column 2 of a known possible nuclide in effluent stream. (The limiting nuclide shall be evaluated annually by reviewing current nuclides against historical ones in order to determine if one with a more restrictive effluent concentration limit than Sr90 is found. The concentration limit shall be adjusted appropriately.)

-OR-

Information I PMP-601 0-OSD-001 I Rev. 27 I Page 31 of 92 OFF-SITE DOSE CALCULATION MANUAL if a mixture is to be specified, Ic I C; LIMIT; Eff = Efficiency, this information is located in Attachment 3 .11, Volumetric Detection Efficiencies for Principle Gamma Emitting Radionuclides for Mirion Liquid Monitors, through Attachment 3.13, Counting Efficiency for 1-WRA-713, 2-WRA-714, l-WRA-717, and 2-WRA-718, for the specific monitors. For Mirian monitors, the efficiency is nuclide specific and the calculation changes slightly to:

L(C;*

- -- Eff)

- rep laces C*E~t+

'JJ I C; LIMIT; MRP = multiple release point factor. A factor such that when all the release points are operating at one time the limits of 10 CFR 20 will not be exceeded (Attachment 3.8, Multiple Release Point Factors for Release Points). The MRP for ESW monitors is set to 1.

F = dilution water (circ water) flow rate in gpm obtained from Attachment 3.10, Plant Liquid Effluent Parameters.

For routine operation, the setpoint should be calculated using the minimum dilution flow rate of 230,000 gpm.

SF = Safety Factor, 0.9.

f = applicable effluent release flow rate in gpm. For routine operation, the setpoint should be calculated using maximum effluent flow rate (Attachment 3.10, Plant Liquid Effluent Parameters).

Information I PMP-601 0-OSD-001 I Rev. 27 I Page 32 of 92 OFF-SITE DOSE CALCULATION MANUAL

3. 3. 2 Gaseous Monitors For the purpose of implementing Step 3.2.2, Radioactive Gaseous Effluent Monitoring Instrumentation, and Substep 3.2.4a, Dose Rate, the alarm setpoints for gaseous effluents released into unrestricted areas will be established using the following methodology. In addition, the above steps do not apply to instantaneous alarm and trip setpoints for integrating radiation monitors sampling radioiodines, radioactive materials in particulate form and radionuclides other than noble gases. A schematic of the gaseous effluent release systems is presented in Attachment 3. 14, Gaseous Effluent Release Systems. Attachment 3.15, Plant Gaseous Effluent Parameters, presents the effluent flow rate parameter(s).

Gaseous effluent monitor high alarm setpoints will routinely be established at a fraction of the maximum allowable setpoint (typically 10% of the setpoint) for ALARA purposes. Alert alarms will normally be set to provide adequate indications of small changes in radiological conditions.

NOTE: IF the setpoint calculation methodology changes or the associated factors change for Unit Vent, Air Ejector and/or Gland Seal monitors, THEN initiate a review by Emergency Planning to ensure that the requirements of 10 CFR 50.54 (q) are maintained .

a. Plant Unit Vent

1. The gaseous effluents discharged from the plant vent will be monitored by the plant vent radiation monitor low (normal) range noble gas channel [VRS-1505A/ VRS-1505B for Unit 1 and VRS-2505A/ VRS-2505B for Unit 2] to assure that applicable alarms and trip actions (isolation of gaseous release) will occur prior to exceeding the limits in step 3.2.4, Gaseous Effluents. The alarm setpoint values will be established using the following unit analysis equation:

SF*MRP* DL

• s = J p Fp

• z!Q*I(w;* DCFij)

Where:

Sp = the maximum setpoint of the monitor in µCi/cc for release point p, based on the most limiting organ SF = an administrative operation safety factor, less than 1.0

Information I PMP-601 0-OSD-001 I Rev. 27 I PaQe 33 of 92 OFF-SITE DOSE CALCULATION MANUAL MRP = a weighted multiple release point factor(~ 1.0), such that when all site gaseous releases are integrated, the applicable dose wi 11 not be exceeded based on the release rate of each effluent point. The MRP is an arbitrary value based on the ratio of the release rate or the volumetric flow rate of each effluent point to the total respective flow rate value of the plant and will be consistent with past operational experience.

The MRP is computed as follows:

• Compute the average release rate, Op, (or the volumetric flow rate, fp) from each release point p.

• Compute rQp (or rfp) for all release points.

• Ratio Qp/rQp (or fp/rfp) for each release point.

This ratio is the MRP for that specific release point

• Repeat the above bullets for each of the site's eight gaseous release points.

Fp = the maximum volumetric flow rate of release point "p",

at the time of the release, in cc/sec. The maximum Unit Vent flow rate, by design, is 186,600 cfm for Unit 1 and 143,400 cfm for Unit 2.

Dlj = dose rate limit to or*gan 'J' in an unrestricted area (mrem/yr).

Based on continuous releases, the dose rate limits, Dlj, from step 3.2.4a, Dose Rate, are as follows:

• Total Body~ 500 mrem/year

• Skin ~ 3000 mrem/year

• Any Organ~ 1500 mrem/year x IQ = The worst case annual average relative concentration in the applicable sector or area, in sec/m 3 (see Attachment 3.16, 10 Year Average of 1995-2004 Data).

Wi = weighted factor for the radionuclide:

w-=__s;_

I LCk Where:

Ci = concentration of the most abundant radionuclide "i" Ck = total concentration of all identified radionuclides in that release pathway. For batch releases, this value may be set to 1 for conservatism.

Information I PMP-601 0-OSD-001 I Rev. 27 I Paoe 34 of 92 OFF-SITE DOSE CALCULATION MANUAL DCFu = dose conversion factor used to relate radiation dose to organ 'J ", from exposure to radionuclide "i" in mrem m3 / yr µCi. See following equations.

The dose conversion factor, DCFu, is dependent upon the organ of concern.

For the whole body: DCFu = Ki Where:

Ki = whole body dose factor due to gamma emissions for each identified noble gas radionuclide in mrem m3 / yr µCi. See Attachment 3.18, Dose Factors.

For the skin:

Where:

Li = skin dose factor due to beta emissions for each identified noble gas radionuclide, in mrem m3 / yr µCi. See Attachment 3.18, Dose Factors.

1.1 = the ratio of tissue to air absorption coefficient over the energy range of photons of interest. This ratio converts absorbed dose (mrad) to dose equivalent (mrem).

Mi = the air dose factor due to gamma emissions for each identified noble gas radionuclide in mrad m3 / yr µCi. See Attachment 3.18, Dose Factors.

For the thyroid, via inhalation: DCFu = Pi Where:

Pi = the dose parameter, for radionuclides other than noble gas, for the inhalation pathway in mrem m3 / yr µCi (and the food and ground path, as appropriate).

See Attachment 3.18, Dose Factors.

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2. The plant vent radiation monitor low (normal) range noble gas high alarm channel setpoint, Sp, will be set such that the dose rate in unrestricted areas to the whole body, skin and thyroid (or any other organ), whichever is most limiting, will be less than or equal to 500 mrem/yr, 3000 mrem/yr, and 1500 mrem/yr respectively.

3. The thyroid dose is limited to the inhalation pathway only.

4. The plant vent radiation monitor low (normal) range noble gas setpoint, Sp, will be recomputed whenever gaseous releases like Containment Purge, Gas Decay Tanks and eves HUTs are discharged through the plant vent to determine the most limiting organ.

5. The high alarm setpoint, Sp, may be established at a lower value than the lowest computed value via the setpoint equation.

6. Containment Pressure Reliefs will not have a recomputed high alarm setpoint, but will use the normal high alarm setpoint due to their randomness and the time constraints involved in recomputation.

7. At certain times, it may be desirable to increase the high alarm setpoint, if the vent flow rate is decreased. This may be accomplished in one of two ways.

Max Cone (µCi/cc)* Max Flowrate (cfm) J\r M ,r,

---

'-..;__---'-------_,;,__:;_---'- = JVeW ax cJm New Max Concentration ( µCi/cc)

-OR-Max Cone (µCi/cc)* Max Flowrate (cfm) J\r M

---

'-..;__---'-------_,;,__:;_----'- = JVew ax µ c*vcc1 New Max F/owrate (cfm)

b. Waste Gas Storage Tanks

1. The gaseous effluents discharged from the Waste Gas System are monitored by the plant vent radiation monitor noble gas channels VRS-1505A/ VRS-15058 for Unit 1 and the channels VRS-2505A/ VRS-25058 for Unit 2.

Information I PMP-601 0-OSD-001 I Rev. 27 I Page 36 of 92 OFF-SITE DOSE CALCULATION MANUAL

2. In the event of a high radiation alarm, an automatic termination of the release from the waste gas system will be initiated from the plant vent radiation monitor low (normal) range noble gas channel VRS-1505A/ VRS-1505B for Unit 1 and VRS-2505A/ VRS-2505B for Unit 2. Therefore, for any gaseous release configuration, which includes normal operation and waste gas system gaseous discharges, the alarm setpoint of the plant vent radiation monitor will be recomputed to determine the most limiting organ based on all gaseous effluent source terms.

Chemical and Volume Control System Hold Up Tanks (CVCS HUT), containing high gaseous oxygen concentrations, may be released under the guidance of waste gas storage tank utilizing approved Operations' procedures.

3. It is normally prudent to allow 45 days of decay prior to releasing a Gas Decay Tank (GDT). There are extenuating, operational circumstances that may prevent this from occurring. Under these circumstances, such as high oxygen concentration creating a combustible atmosphere, it is prudent to waive the 45-day decay for safety's sake.

c. Containment Purge and Exhaust System

1. The gaseous effluents discharged by the Containment Purge and Exhaust Systems and Instrumentation Room Purge and Exhaust System are monitored by the plant vent radiation monitor noble gas channels VRS-1505A/ VRS-1505B for Unit 1 and VRS-2505A/

VRS-2505B for Unit 2; and alarms and trip actions will occur prior to exceeding the limits in step 3.2.4a, Dose Rate.

2. For the Containment System, a continuous air sample from the containment atmosphere is drawn through a closed, sealed system to the radiation monitors ( ERS-1300/1400 for Unit 1 and ERS-2300/2400 for Unit 2). During purges, these monitor setpoints will give a Purge and Exhaust Isolation signal upon actuation of high alarm setpoints for particulate and noble gas channels. The sample is then returned to containment. Grab sample analysis is performed for a Containment purge before release.

3. The Upper Containment area is monitored by normal range area gamma monitors (VRS-1101/1201 for Unit 1 and VRS-2101/2201 for Unit 2), which also give Purge and Exhaust Isolation Trip signals upon actuation of their high alarm.

4. For the Containment Pressure Relief System, no sample is routinely taken prior to release, but a sample is obtained twice per month.

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5. The containment airborne and area monitors, upon actuation of their high alarm, will automatically initiate closure of the Containment and Instrument Room purge supply and exhaust duct valves and containment pressure relief system valves. Complete trip of all isolation control devices requires high alarm of one of the two Train A monitors (ERS-1300/2300 or VRS-1101/2101) and one of the two Train B monitors (ERS-1400/2400 or VRS-1201/2201).

d. Steam Jet Air ~ector System (SJAE)

1. The gaseous effluents from the Steam Jet Air Ejector System discharged to the environment are continuously monitored by radiation monitor (Tag No. SRA-1900 for Unit 1 and SRA-2900 for Unit 2). The monitor will alarm prior to exceeding the limits of step 3.2.4a, Dose Rate. The alarm setpoint for the Condenser Air Ejector System monitor will be based on the maximum air ejector exhaust flow rate, (Attachment 3.15, Plant Gaseous Effluent Parameters). The alarm setpoint value wi II be established using the following unit analysis equation:

SF*MRP* DL

• s = J SJAE F p

• x,/iQ * "L.J ( W;

• DCFii )

i Where:

SsJAE = the maximum setpoint, based on the most limiting organ, in µCi/cc and where the other terms are as previously defined

e. Gland Seal Condenser Exhaust

1. The gaseous effluents from the Gland Seal Condenser Exhaust discharged to the environment are continuously monitored by radiation monitor (Tag No. SRA-1800 for Unit 1 and SRA-2800 for Unit 2). The radiation monitor will alarm prior to exceeding the limits of step 3.2.4a, Dose Rate. The alarm setpoint for the GSCE monitor wi II be based on the maximum condenser exhaust flow rate (1260 CFM for Unit 1, 2754 CFM each for the two Unit 2 vents).

The alarm setpoint value will be established using the following unit analysis equation:

SF*MRP* DL

• s = J GSCE Fp

• z1,.IQ * "L.J ( W;

• DCFiJ )

i

Information I PMP-601 0-OSD-001 I Rev. 27 I Paqe 38 of 92 OFF-SITE DOSE CALCULATION MANUAL Where:

SGscE = the maximum setpoint, based on the most limiting organ, in µCi/cc and where the other terms are as previously defined 3.4 Radioactive Effluents Total Dose 3.4.1 The cumulative dose contributions from liquid and gaseous effluents will be determined by summing the cumulative doses as derived in steps 3.2.3c (Dose), 3.2.4b (Dose - Noble Gases), and 3.2.4c (Dose - lodine-131, lodine-133, Tritium, and Radioactive Material in Particulate Form) of this procedure. Dose contribution from direct radiation exposure will be based on the results of the direct radiation monitoring devices located at the REMP monitoring stations, and reflects direct dose both from the Dry Cask Storage Facility (ISFSI) licensed under Holtech International and both units of Cook.

See NUREG-0133, section 3.8.

3.5 Radiological Environmental Monitoring Program (REMP) 3.5.1 Purpose of the REMP

a. The purpose of the REMP is to:

• Establish baseline radiation and radioactivity concentrations in the environs prior to reactor operations,

• Monitor critical environmental exposure pathways,

• Determine the radiological impact, if any, caused by the operation of the Donald C. Cook Nuclear Plant upon the local environment.

• Assist with fulfilling the requirements of the Groundwater Protection Initiative (GPI).

Information I PMP-601 0-OSD-001 I Rev. 27 I Page 39 of 92 OFF-SITE DOSE CALCULATION MANUAL

b. The first purpose of the REMP was completed prior to the initial operation of either of the two nuclear units at the Donald C. Cook Nuclear Plant Site. The remaining purposes of the REMP are an on-going operation and as such various environmental media and exposure pathways are examined. The various pathways and sample media used are delineated in Attachment 3.19, Radiological Environmental Monitoring Program Sample Stations, Sample Types, Sample Frequencies. Included is a list of the sample media, analysis required, sample stations, and frequency requirements for both collection and analysis. Attachment 3.19, Radiological Environmental Monitoring Program Sample Stations, Sample Types, Sample Frequencies, defines the scope of the REMP for the Donald C. Cook Nuclear Plant.

3.5.2 Conduct of the REMP [Ref. 5.2. 1t]

a. Conduct sample collection and analysis for the REMP in accordance with Attachment 3.19, Radiological Environmental Monitoring Program Sample Stations, Sample Types, Sample Frequencies, Attachment 3.20, Maximum Values for Lower Limits of Detections A*B - REMP, and Attachment 3.21, Reporting Levels for Radioactivity Concentrations in Environmental Samples. These are applicable at all times. The on-site monitoring locations are shown on Attachment 3.22, On-Site Monitoring Location - REMP, and the off-site monitoring locations are shown on Attachment 3.23, Off-Site Monitoring Locations - REMP.

1. Perform each surveillance requirement within the specified time interval in Attachment 3.19, Radiological Environmental Monitoring Program Sample Stations, Sample Types, Sample Frequencies, with a maximum allowable extension not to exceed 25% of the surveillance interval.

2. If an environmental sample cannot be collected in accordance with step 3.5.2a, submit a description of the reasons for deviation and the actions taken to prevent a reoccurrence as part of the Annual Radiological Environmental Operating Report (ARE OR).

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3. Deviations from the required sampling schedule are permitted if specimens are unobtainable due to hazardous conditions, seasonal unavailability, or malfunction of automatic sampling equipment. If the deviation from the required sampling schedule is due to the malfunction of automatic sampling equipment, make every effort to complete the corrective action prior to the end of the next sampling period.

NOTE: Only one report per event is required.

NOTE: Radioactivity from sources other than plant effluents do not require a Special Report.

4. IF any of the following conditions are identified:

• A radionuclide associated with plant effluents is detected in any REMP sample medium AND its concentration exceeded the limits specified in Attachment 3.21, Reporting Levels for Radioactivity Concentrations in Environmental Samples,

• More than one radionuclide associated with plant effluents is detected in any REMP sample medium AND the Total Fractional Level, when averaged over the calendar quarter, is greater than or equal to 1.

THEN complete the following steps, as applicable:

• Submit a Special Report to the Nuclear Regulatory Commission within 30 days.

• Submit a Special Report to designated state and local organizations for groundwater or surface water media which could be used as drinking water.

• Evaluate the following items for inclusion in Special Reports:

1) Release conditions

2) Environmental factors

3) Corrective actions

4) Additional factors which may have contributed to the identified levels

Information I PMP-6010-OSD-001 I Rev. 27 I PaQe 41 of 92 OFF-SITE DOSE CALCULATION MANUAL

5. WHEN submission of a Special Report to designated state and local organizations is required, THEN perform the following:

• Communicate event specific information to designated state and local organization personnel by the end of the next business day.

• Document the notification using PMP-6090-PCP-100, Data Sheet 2, Part 4 Radioactive Liquid Spill Which May Impact Groundwater.

• Forward a copy of the notification to the Environmental Department Manager.

6. IF a currently sampled milk farm location becomes unavailable, THEN conduct a special milk farm survey within 15 days.

a) IF the unavai Iable location was an indicator farm, TH EN an alternate sample location may be established within eight miles of the Donald C . Cook Nuclear Plant, if one is available.

b) IF the unavailable location was a background farm, THEN an alternate sample location may be established greater than 15 but less than 25 miles of the Donald C. Cook Nuclear Plant in one of the less prevalent wind direction sectors, if one is available.

c) IF a replacement farm is unobtainable and the total number of indicator farms is less than three or the background farms is less than one, THEN perform monthly vegetation sampling in lieu of milk sampling when vegetation is available.

BASES - RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

The REMP provides measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides, which lead to the highest potential radiation exposures of individuals resulting from the station operation. Thereby, this monitoring program supplements the radiological effluent monitoring program by verifying the measurable concentration of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. The initially specified REMP was effective for the first three years of commercial operation . Program changes may be initiated based on operational experience in accordance with the requirements of Technical Specification 5.5 .1.c.

The detection capabilities, required by Attachment 3.20, Maximum Values for Lower Limits of Detections A*B - REMP, are the state-of-the-art for routine environmental measurements in industrial laboratories.

Information I PMP-6010-OSD-001 I Rev. 27 I Page 42 of 92 OFF-SITE DOSE CALCULATION MANUAL It should be recognized that the LLD is defined as a priori (before the fact) limit representing the capability of a measurement system and not as a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine analysis conditions. Occasionally, background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.

3.5.3 Annual Land Use Census [Ref. 5.2.1t]

a. Conduct a land use census and identify the location of the nearest milk animal, the nearest residence and the nearest garden of greater than 500 square feet producing fresh leafy vegetables in each of the ten land sectors within a distance of five miles.

b. In lieu of the garden census, broad leaf vegetation sampling of at least three different kinds of vegetation (if available) may be performed as close to the site boundary as possible (within 5 miles) in each of two different direction sectors with the highest average deposition factor (D/Q) value .

c. Conduct this land use census annually between the dates of June 1 and October 1 by door-to-door survey, aerial survey, or by consulting local agricultural authorities.

1. With a land use census identifying a location(s), which yields a calculated dose or dose commitment greater than the values currently being calculated in this document, make appropriate changes to incorporate the new location(s) within 30 days, if possible .

BASES - LAND USE CENSUS This is provided to ensure changes in the use of unrestricted areas are identified and modifications to the monitoring program are made, if required by the results of the census.

This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.

Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used: 1) that 20% of the garden was used for growing broad leaf vegetation (that is, similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/square meter.

3.5.4 lnterlaboratory Comparison Program

a. In order to comply with Reg. Guides 4.1 and 4.15, the analytical vendor participates in an lnterlaboratory Comparison Program, for radioactive materials. Address program results and identified deficiencies in the AREOR.

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1. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the AREOR.

BASES - INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an lnterlaboratory Comparison Program is provided to ensure independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate the results are reasonably valid.

3.6 Meteorological Model 3.6 .1 Three towers are used to determine the meteorological conditions at Donald C .

Cook Nuclear Plant. One of the towers is located at the Lake Michigan shoreline to determine the meteorological parameters associated with unmodified shoreline air. The data is accumulated by microprocessors at the tower sites and normally transferred to the central computer every 15 minutes .

3.6.2 The central computer uses a meteorological software program to provide atmospheric dispersion and deposition parameters . The meteorological model used is based on guidance provided in Reg. Guide 1.111 for routine releases. All calculations use the Gaussian plume model.

3. 7 Reporting Requirements

3. 7 .1 Annual Radiological Environmental Operating Report (AREOR)

a. Submit routine radiological environmental operating reports covering the operation of the units during the previous calendar year prior to May 15 of each year. [Ref 5.2.1j, TS 5.6.2]

b. Include in the AREOR :

• Summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activities for the reporting period.

• A comparison with pre-operational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment.

• The results of the land use censuses required by step 3.5.3, Annual Land Use Census .

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• If harmful effects or evidence of irreversible damage are detected by the monitoring, provide in the report an analysis of the problem and a planned course of action to alleviate the problem.

• Summarized and tabulated results of all radiological environmental samples taken during the reporting period. In the event that some results are not available for inclusion with the report, submit the report noting and explaining the reasons *for the missing results.

Submit the missing data as soon as possible in a supplementary report.

• A summary description of the REMP including sampling methods for each sample type, size and physical characteristics of each sample type, sample preparation methods, analytical methods, and measuring equipment used.

• A map of all sample locations keyed to a table giving distances and directions from one reactor.

• The results of participation in the lnterlaboratory Comparison Program required by step 3.5.4, lnterlaboratory Comparison Program.

• The results of non-REMP samples taken for informational purposes in support of non-program specific investigations, such as rainfall studies of tritium recapture for example.

3. 7 .2 Annual Radiological Effluent Release Report (ARE RR)

a. Submit routine ARERR covering the operation of the unit during the previous 12 months of operation prior to May 1st of each year. [Ref 5. 2.1j, TS 5.6.3]

b. Include in the ARERR a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the units as outlined in Reg. Guide 1.21, "Measuring, Evaluating and Reporting in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water Cooled Nuclear Power Plants," with data summarized on a quarterly basis following the format of Appendix B, thereof.

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c. Submit in the ARERR prior to May ,st of each year and include a quarterly summary of hourly meteorological data collected during the reporting period.

• This summary may be in the form of an hour-by-hour listing of wind speed, wind direction, atmospheric stability, and precipitation (if measured) on magnetic tape, or in the form ofjoint frequency distributions of wind speed, wind direction and atmospheric stability.

• Include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year.

• Include an assessment of the radiation doses from radioactive liquid and gaseous effluents to members of the public due to their activities inside the site boundary during the reporting period. Include all assumptions used in making these assessments (that is, specific activity, exposure time and location) in these reports.

• Use the meteorological conditions concurrent with the time of release of radioactive materials in gaseous effluents (as determined by sampling frequency and measurement) for determining the gaseous pathway doses.

• Inoperable radiation monitor periods exceeding 30 continuous days; explain causes of inoperability and actions taken to prevent reoccurrence.

d. Submit the ARERR [Ref. 5.2.1v] prior to May 1st of each year and include an assessment of radiation doses to the likely most exposed member of the public from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) for the previous 12 consecutive months to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operation. Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Reg. Guide 1.109, Rev.1.

e. Include in the ARERR the following information for each type of solid waste shipped off-site during the report period:

• Volume (cubic meters),

• Total curie quantity (specify whether determined by measurement or estimate),

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• Principle radionuclides (specify whether determined by measurement or estimate),

• Type of waste (example: spent resin, compacted dry waste, evaporator bottoms),

• Type of container (example: LSA, Type A, Type B, Large Quantity),

-AND-

• Solidification agent (example: cement).

f. Include in the ARERR unplanned releases of radioactive materials in gaseous and liquid effluent from the site to unrestricted areas on a quarterly basis.

g. Include in the ARERR any change to this procedure made during the reporting period.

h. Due to the site having shared gaseous and liquid waste systems dose calculations will be performed on a per site bases using the per unit values. This is A LARA and wi II ensure comp I iance with 40 CFR 141, National Primary Drinking Water Regulations. Unit specific values are site values divided by two.

i. Include in the ARERR groundwater sample results taken that are in support of the Groundwater Protection Initiative (GPI) but are not part of the REMP.

3.8 10 CFR 50. 75 (g) Implementation 3.8.1 Records of spills or other unusual occurrences involving the spread of contamination in and around the site. These records may be limited to instances when significant contamination remains after decontamination or when there is a reasonable likelihood that contaminants may have spread to inaccessible areas, as in the case of possible seepages.

3.8.2 These records shall include any known information or identification of involved nuclides, quantities, and concentrations.

3.8.3 This information is necessary to ensure all areas outside the radiological-restricted area are documented for surveying and remediation during decommissioning. There is a retention schedule item for 10 CFR 50. 75(g) where this information is filed in Nuclear Documents Management to ensure all required areas are listed to prevent their omission.

Information I PMP-601 0-OSD-001 I Rev. 27 I Pa~e 47 of 92 OFF-SITE DOSE CALCULATION MANUAL 3.9 Reporting/Management Review 3.9.1 Incorporate any changes to this procedure in the ARERR.

3.9.2 Update this procedure when required for changes made to the Radiation Monitoring System, its instruments, or the specifications of instruments.

3.9.3 Review or revise this procedure as appropriate based on the results of the land use census and REMP .

3.9.4 Consider any changes to this procedure for potential impact on other related Department Procedures.

3.9.5 Review the past year's meteorological data during the first quarter of each year and update the ODCM as necessary. Review Attachment 3.16, 10 Year Average of 1995-2004 Data, and document using Attachment 3.17, Annual Evaluation of x/Qand D/QvaluesForAllSectors. The z!Q and D/Qvalueswill be processed using +/- 3 standard deviations of the data and evaluated against the 10 year annual average data. Documentation is done by completing Attachment 3.17, Annual Evaluation of x /Q and D/Q Values For All Sectors, and filed in accordance with the retention schedule.

4 FINAL CONDITIONS 4.1 None.

5 REFERENCES 5.1 Use

References:

5.1.1 "Implementation of Programmatic Controls for Radiological Effluent Technical Specifications in the Administrative Controls Section of the Technical Specifications and the Relocation of Procedural Details of RETS to the Off-Site Dose Calculation Manual or to the Process Control Program (Generic Letter 89-01)", United States Nuclear Regulatory Commission, January 31, 1989 5.1.2 12-THP-6010-RPP-601, Preparation of the Annual Radioactive Effluent Release Report 5.1.3 12-THP-6010-RPP-639, Annual Radiological Environmental Operating Report (AREOR) Preparation And Submittal 5.1.4 PMP-6090-PCP-100, Spill Response- Oil, Polluting, Hazardous Materials, and Radioactive Spills

Information I PMP-6010-OSO-001 I Rev. 27 I Paqe 48 of 92 OFF-SITE DOSE CALCULATION MANUAL 5.2 Writing

References:

5.2.1 Source

References:

a. 10 CFR 20, Standards for Protection Against Radiation

b. 10 CFR 50, Domestic Licensing of Production and Utilization Facilities

c. PMl-6010, Radiation Protection Plan

d. NUREG-0472

e. NUREG-1301

f. NUREG-0133

g. Regulatory Guide 1.109, non-listed parameters are taken from these data tables

h. Regulatory Guide 1.111

i. Regulatory Guide 1 .113

j. Updated Final Safety Analysis Report (UFSAR)

k. Technical Specifications 5.4.1.e, 5.5.1.c, 5.5.3, 5.6.2, and 5.6.3 I. Final Environmental Statement Donald. C. Cook Nuclear Plant, August 1973

m. NUREG-0017

n. ODCM Setpoints for Liquid [and Gaseous] Effluent Monitors (Bases),

ENGR 107-04 8112.1 Environs Rad Monitor System

o. HPPOS-223, Consideration of Measurement Uncertainty When Measuring Radiation Levels Approaching Regulatory Limits

p. 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operations

q. NRC Commitment 6309 (N94083 dated 11/10/94)

r. NRC Commitment 1151

s. NRC Commitment 1217

t. NRC Commitment 3240

u. NRC Commitment 3850

v. NRC Commitment 4859

Information I PMP-6010-OSD-001 I Rev. 27 I PaQe 49 of 92 OFF-SITE DOSE CALCULATION MANUAL

w. NRC Commitment 6442

x. NRC Commitment 3768

y. DIT-B-00277-00, HVAC Systems Design Flows

z. Regulatory Guide 1.21 aa. Regulatory Guide 4.1 bb . 1-2-V3-02-Calc #4, Unit Vent Sample Flow rate for isokinetic particulates and Iodine sampling cc. HPS N13.30-1996, Appendix A Rationale for Methods of Determining Minimum Detectable Amount (MDA) and Minimum Testing Level (MDL dd . DIT-B-01971-00, Dose Factors for Radioactive Particulate Gaseous Effluents Associated with the Child by the Inhalation Pathway ee. DIT-B-01987-00, Ground Plane & Food Dose Factors Pi for Radioiodines and Radioactive Particulate Gaseous Effluents ff. NRC Commitment 1010 gg. NEI 07-07 Groundwater Protection Initiative hh. ANI 07-01 Potential for Unmonitored and Unplanned Off-Site Releases of Radioactive Material ii. RD-16-03, Mirian MCNPX Analysis Report 5.2.2 General References

a. Cook Nuclear Plant Start-Up Flash Tank Flow Rate letter from D. L.

Boston dated January 21, 1997

b. Letter from B.P. Lauzau, Venting of Middle eves Hold-Up Tank Directly to Unit Vent, May 1, 1992

c. AEP Design Information Transmittal on Aux Building Ventilation Systems

d. PMP-4030.EIS.001, Event-Initiated Surveillance Testing

e. Environmental Position Paper, Fe Impact on Release Rates, approved 3/14/00

f. Environmental Position Paper, Methodology Change from Sampling Secondary System Gaseous Effluents for Power Changes Exceeding 15% within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to Responding to Gaseous Alert Alarms, approved 4/4/00.

Information I PMP-601 0-OSD-001 I Rev. 27 I PaQe 50 of 92 OFF-SITE DOSE CALCULATION MANUAL

g. CR 02150078, RRS-1000 efficiency curve usage

h. Environmental Position Paper, Unit Vent Compensatory Sampling, approved 4/14/05 Remainder of this page left blank intentionally

Information PMP-601 0-OSD-001 I Rev. 27 PaQe 51 of 92 OFF-SITE DOSE CALCULATION MANUAL Pages:

Attachment 3.1 Dose Factors for Various Pathways 51 - 54 Ri Dose Factors PATHWAY Nuclide Ground Ve2etable Meat Cow Milk Goat Milk Inhalation H-3 0.0E+o0 4.0E+03 3.3E+o2 2.4E+03 4.9E+o3 1.3E+o3 C-14 0.0E+00 3.5E+06 5.3E+05 3.2E+06 3.2E+06 3.6E+04 Cr-51 5.4E+o6 1.1E+o7 1.5E+o6 6.9E+o6 8.3E+o5 2.1E+o4 Mn-54 l.6E+09 9.4E+08 2.1E+07 2.9E+07 3.5E+o6 2.0E+06 Fe-59 3.2E+o8 9.6E+08 l.7E+09 3.1E+08 4.0E+o7 l.5E+06 Co-58 4.4E+08 6.0E+o8 2.9E+o8 8.4E+07 1.0E+o7 l.3E+o6 Co-60 2.5E+10 3.2E+09 l.0E+09 2.7E+08 3.2E+07 8.6E+06 Zn-65 8.5E+o8 2.7E+o9 9.5E+o8 1.6E+10 1.9E+o9 l.2E+o6 Sr-89 2.5E+04 3.5E+10 3.8E+08 9.9E+09 2.lE+lO 2.4E+06 Sr-90 0.0E+o0 l.4E+12 9.6E+o9 9.4E+10 2.0E+ll l.1E+o8 Zr-95 2.9E+08 l.2E+09 l.5E+09 9.3E+05 1.1E+o5 2.7E+06 Sb-124 6.9E+08 3.0E+09 4.4E+08 7.2E+08 8.6E+07 3.8E+06 I-131 1.0E+07 2.4E+10 2.5E+o9 4.8E+l 1 5.8E+l 1 1.6E+o7 I-133 l.5E+06 4.0E+08 6.0E+0l 4.4E+09 5.3E+09 3.8E+o6 Cs-134 7.9E+o9 2.5E+10 l.1E+09 5.0E+lO 1.5E+l 1 1.1E+o6 Cs-136 l.7E+08 2.2E+08 4.2E+07 5.1E+09 1.5E+10 l.9E+05 Cs-137 l.2E+10 2.5E+l0 1.0E+o9 4.5E+10 1.4E+l 1 9.0E+05 Ba-140 2.3E+07 2.7E+08 5.2E+07 2.1E+08 2.6E+07 2.0E+06 Ce-141 l.5E+07 5.3E+o8 3.0E+07 8.3E+07 1.0E+07 6.1E+05 Ce-144 7.9E+07 l.3E+10 3.6E+08 7.3E+08 8.7E+07 l.3E+07 Units for all except inhalation pathway are m2 mr sec I yr µCi, inhalation pathway units are mr m3 I yr µCi.

Uap Values to be Used For the Maximum Exposed Individual Pathway Infant Child Teen Adult Fruits, vegetables and grain (kg/yr) -- 520 630 520 Leafy vegetables (kg/yr) -- 26 42 64 Milk (L/yr) 330 330 400 310 Meat and poultry (kg/yr) -- 41 65 110 Fish (kg/yr) -- 6.9 16 21 Drinking water (L/yr) 330 510 510 730 Shoreline recreation (hr/yr) -- 14 67 12 Inhalation (m 3/yr) 1400 3700 8000 8000 Table E-5 of Reg. Guide 1.109.

Information PMP-6010-OSD-001 I Rev. 27 Page 52 of 92 OFF-SITE DOSE CALCULATION MANUAL Pages: .1 Dose Factors for Various Pathways 51 - 54 Bip Factors for Aquatic Foods pCi I/ kg pCi Element Fish Invertebrate H 9.0E-1 9.0E-1 C 4.6E3 9.1E3 Na 1.0E2 2.0E2 p 1.0ES 2.0E4 Cr 2.0E2 2.0E3 Mn 4.0E2 9.0E4 Fe 1.0E2 3.2E3 Co 5.0E1 2.0E2 Ni 1.0E2 1.0E2 Cu 5.0E1 4.0E2 Zn 2.0E3 1.0E4 Br 4.2E2 3.3E2 Rb 2.0E3 1.0E3 Sr 3.0E1 1.0E2 y 2.5E1 1.0E3 Zr 3.3E0 6.7E0 Nb 3.0E4 1.0E2 Mo 1.0E1 1.0E1 Tc 1.5E1 5.0E0 Ru 1.0E1 3.0E2 Rh 1.0E1 3.0E2 Te 4.0E2 6.1E3 I 1.5E1 5.0E0 Cs 2.0E3 1.0E3 Ba 4.0E0 2.0E2 La 2.5E1 1.0E3 Ce 1.0E0 1.0E3 Pr 2.5E1 1.0E3 Nd 2.5E1 1.0E3 w 1.2E3 1.0E1 Np 1.0E1 4.0E2 Table A-1 of Reg. Guide 1.109.

Information PMP-601 0-OSD-001 I Rev. 27 Page 53 of 92 OFF-SITE DOSE CALCULATION MANUAL Pages: .1 Dose Factors for Various Pathways 51 - 54 Daipj External Dose Factors for Standing on Contaminated Ground mrem m2 I hr pCi Radionuclide Total Bodv Skin H-3 0 0 C-14 0 0 Na-24 2.SE-8 2.9E-8 P-32 0 0 Cr-51 2.2E-10 2.6E-10 Mn-54 5.BE-9 6.BE-9 Mn-56 1.1 E-8 1.3E-8 Fe-55 0 0 Fe-59 8.0E-9 9.4E-9 Co-58 7.0E-9 8.2E-9 Co-60 1. 7E-8 2.0E-8 Ni-63 0 0 Ni-65 3.7E-9 4.3E-9 Cu-64 1.SE-9 1. 7E-9 Zn-65 4.0E-9 4.6E-9 Zn-69 0 0 Br-83 6.4E-11 9.3E-11 Br-84 1.2E-8 1.4E-8 Br-85 0 0 Rb-86 6.3E-10 7.2E-10 Rb-88 3.SE-9 4.0E-9 Rb-89 1.SE-8 1.BE-8 Sr-89 5.6E-13 6.SE-13 Sr-91 7.1 E-9 8.3E-9 Sr-92 9.0E-9 1.0E-8 Y-90 2.2E-12 2.6E-12 Y-91m 3.BE-9 4.4E-9 Y-91 2.4E-11 2.7E-11 Y-92 1.6E-9 1.9E-9 Y-93 5. 7E-10 7.BE-10 Zr-95 5.0E-9 5.BE-9 Zr-97 5.5E-9 6.4E-9 Nb-95 5.1 E-9 6.0E-9 Mo-99 1.9E-9 2.2E-9 Tc-99m 9.6E-10 1.1 E-9 Tc-101 2.7E-9 3.0E-9 Ru-103 3.6E-9 4.2E-9 Ru-105 4.5E-9 5.1 E-9 Ru-106 1.5E-9 1.BE-9 Ag-110m 1.BE-8 2.1 E-8 Te-125m 3.SE-11 4.BE-11

Information PMP-601 0-OSD-001 I Rev. 27 Paqe 54 of 92 OFF-SITE DOSE CALCULATION MANUAL Pages: .1 Dose Factors for Various Pathways 51 - 54 Radionuclide Total Body Skin Te-127m 1.1E-12 1.3E-12 Te-127 1.0E-11 1.1E-11 Te-129m 7.7E-10 9.0E-10 Te-129 7.1E-10 8.4E-10 Te-131m 8.4E-9 9.9E-9 Te-131 2.2E-9 2.6E-6 Te-132 1.7E-9 2.0E-9 1-130 1.4E-8 1. 7E-8 1-131 2.BE-9 3.4E-9 1-132 1. 7E-8 2.0E-8 1-133 3.7E-9 4.5E-9 1-134 1.6E-8 1.9E-8 1-135 1.2E-8 1.4E-8 Cs-134 1.2E-8 1.4E-8 Cs-136 1.5E-8 1.7E-8 Cs-137 4.2E-9 4.9E-9 Cs-138 2.1 E-8 2.4E-8 Ba-139 2.4E-9 2.7E-9 Ba-140 2.1 E-9 2.4E-9 Ba-141 4.3E-9 4.9E-9 Ba-142 7.9E-9 9.0E-9 La-140 1.5E-8 1.7E-8 La-142 1.5E-8 1.BE-8 Ce-141 5.5E-10 6.2E-10 Ce-143 2.2E-9 2.5E-9 Ce-144 3.2E-10 3.7E-10 Pr-143 0 0 Pr-144 2.0E-10 2.3E-10 Nd-147 1.0E-9 1.2E-9 W-187 3.1E-9 3.6E-9 Np-239 9.5E-10 1.1 E-9 Table E-6 of Reg . Guide 1.109.

Information PMP-601 0-OSD-001 I Rev. 27 I PaQe 55 of 92 OFF-SITE DOSE CALCULATION MANUAL Pages:

Attachment 3 .2 Radioactive Liquid Effluent Monitoring Instruments 55 - 57 INSTRUMENT Minimum Applicability Action Channels Operablea

1. Gross Radioactivity Monitors Providing Automatic Release Termination

a. Mirian Liquid Radwaste (1) At times of release 1 Effluent Line (RRS-1001-A, RRS-1021-B)

b. Mirian Steam Generator (1) At times of release** 2 Slowdown Line (DRA-300)

C. Mirian Steam Generator (1) At times of release 2 Slowdown Treatment Effluent (DRA-353)

2. Gross Radioactivity Monitors Not Providing Automatic Release Termination

a. Mirian Service Water (1) per At all times 3 System Effluent Line (Unit 1:WRA-713, train WRA-717) and (Unit 2: WRA-714, WRA-718)

3. Continuous Composite Sampler Flow Monitor

a. Turbine Building Sump (1) At all times 3 Effluent Line

4. Flow Rate Measurement Devices

a. Liquid Radwaste Line (1) At times of release 4 (RFl-285)

b. Discharge Pipes* (1) At all times NA C. Steam Generator Slowdown (1) At times of release 4 Treatment Effluent (DFl-352)

d. Individual Steam Generator sample flow (1) per At times of release 5 to Slowdown radiation monitors alarm generator (DFA-310, 320, 330 and 340)

• Pump curves and valve settings may be utilized to estimate flow; in such cases, Action Statement 4 is not applicable. This is primarily in reference to start up flash tank flow.

• • Since these monitors can be used for either batch or continuous release the appropriate action statement of 1 or 2 should apply (that is, Action 1 if a steam generator drain is being performed in lieu of Action 2). It is possible, due to the steam generator sampling system lineup, that BOTH action statements are actually entered. This would be the case when sampling for steam generator draining requires duplicate samples while the sample system is lined up to discharge to the operating units blowdown system. In this case the steam generator drain samples can fulfill the sample requirement for Action 2 also. Action 2 would be exited when sampling was terminated .

Information PMP-601 0-OSD-001 I Rev. 27 I Paqe 56 of 92 OFF-SITE DOSE CALCULATION MANUAL Pages:

Attachment 3 .2 Radioactive Liquid Effluent Monitoring Instruments 55 - 57 a IF an RMS monitor is inoperable solely as the result of the loss of its control room alarm annunciation, TH EN one of the following actions is acceptable to satisfy the ODCM action statement compensatory surveillance requirement:

1. Collect grab samples and conduct laboratory analyses per the specific monitor's action statement,

-OR-

2. Collect local monitor readings at a frequency equal to or greater than (more frequently than) the action frequency.

IF the RMS monitor is inoperable for reasons other than the loss of control room annunciation, THEN the only acceptable action is taking grab samples and conducting laboratory analyses as the reading is equivalent to a grab sample when the monitor is functional.

TABLE NOTATION Action 1 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases may continue, provided that prior to initiating a release:

1. At least two independent samples (taken at different times) are analyzed in accordance with Step 3.2 .3a and;

2. At least two technically qualified members of the Facility Staff independently verify the discharge valve lineup. Otherwise, suspend release of radioactive effluents via this pathway.

Action 2 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10-7 µCi/gram:

1. At least once per shift when the specific activity of the secondary coolant is > 0.01 µCi/gram DOSE EQUIVALENT 1-131.

2. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the specific activity of the secondary coolant is ~ 0.01 µCi/gram DOSE EQUIVALENT 1-131.

After 30 days, IF the channels are not OPERABLE, THEN continue releases with required grab samples provide a description of why the inoperability was not corrected in the next Annual Radiological Effluent release Report.

Action 3 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that at least once per shift, grab samples are collected and analyzed for gross radioactivity (beta or gamma) at a lower limit of detection of at least 10-7 µCi/ml. Since the Mirion ESW monitors (WRA-713/717 U1 and WRA-714/718 U2) are only used for post LOCA leak detection and have no auto trip function associated with them, grab samples are only needed if the Containment Spray Heat Exchanger is in service. After 30 days, IF the channels are not OPERABLE, THEN continue releases with grab samples once per shift and provide a description of why the inoperability was not corrected in the next Annual Radiological Effluent release Report.

Action 4 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. After 30 days, IF the channels are not OPERABLE, THEN continue releases with flow rate estimates once every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases and provide a description of why the inoperability was not corrected in the next Annual Radiological Effluent release Report.

Information PMP-601 0-OSD-001 I Rev. 27 I PaQe 57 of 92 OFF-SITE DOSE CALCULATION MANUAL Pages:

Attachment 3.2 Radioactive Liquid Effluent Monitoring Instruments 55 - 57 Action 5 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is verified to be within the required band at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. After 30 days, IF the channels are not OPERABLE, THEN continue releases with grab samples once per shift and provide a description of why the inoperability was not corrected in the next Annual Radiological Effluent release Report. IF the flow cannot be obtained within the desired band, THEN declare the radiation monitor inoperable and enter the appropriate actions statement, Action 2.

Compensatory actions are governed by PMP-4030-EIS-001, Event-Initiated Surveillance Testing Rest of page left blank intentionally

Information PMP-601 O-OSD-001 I Rev. 27 PaQe 58 of 92 OFF-SITE DOSE CALCULATION MANUAL Radioactive Liquid Effluent Monitoring Pages:

Attachment 3.3 Instrumentation Surveillance Requirements 58 - 59 Instrument CHANNEL SOURCE CHANNEL CHANNEL CHECK CHECK CALIBRATION OPERATIONAL TEST

1. Gross Radioactivity Monitors Providing Automatic Release Termination

a. Mirian Liquid D* p 8(3) Q(5)

Radwaste Effluent Line (RRS-1001-A, RRS-1021-B)

b. Steam Generator D* M 8(3) Q(1)

Blowdown Effluent Line C. Steam Generator D* M 8(3) Q(1)

Blowdown Treatment Effluent Line

2. Gross Radioactivity Monitors Not Providing Automatic Release Termination

a. Service Water D M 8(3) Q(2)

System Effluent Line

3. Continuous Composite Samplers

a. Turbine Building D* N/A N/A N/A Sump Effluent Line

4. Flow Rate Measurement Devices

a. Liquid Radwaste D(4)* N/A B Q Effluent

b. Steam Generator D(4)* N/A N/A N/A Slowdown Treatment Line

• During releases via this pathway. This is applicable to all surveillances for the appropriate monitor.

Information PMP-601 0-OSD-001 I Rev. 27 PaQe 59 of 92 OFF-SITE DOSE CALCULATION MANUAL Radioactive Liquid Effluent Monitoring Pages:

Attachment 3.3 Instrumentation Surveillance Requirements 58 - 59 TABLE NOTATION

1. Demonstrate with the CHANNEL OPERATIONAL TEST that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm/trip setpoint.

2. Circuit failure .*

3. Instrument indicates a downscale failure .*

4. Instrument control not set in operating mode .*

2. Demonstrate with the CHANNEL OPERATIONAL TEST that control room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm setpoint.

2. Circuit failure.

3. Instrument indicates a downscale failure .

4. Instrument controls not set in operating mode.

3. Perform the initial CHANNEL CALIBRATION using one or more sources with traceability back to the National Institute of Standards and Technology (NIST) . These sources permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration may be used.

4. Verify indication of flow during periods of release with the CHANNEL CHECK . Perform the CHANNEL CHECK at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic or batch releases are made .

5. Demonstrate with the CHANNEL OPERATIONAL TEST that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm/trip setpoint (either detector)

2. Circuit failure of BOTH detectors.* *

3. Instruments indicates a downscale fa ilure for BOTH detectors.**

4. Instrument control not set in operating mode for BOTH detectors.*

• Instrument indicates, but does not provide for automatic isolation

• • Instrument indicates, but does not necessarily cause automatic isolation. No credit is taken for the automatic isolation on such occurrences.

Operations currently performs the routine channel checks and source checks. Maintenance and Radiation Protection perform channel calibrations and channel operational tests. Chemistry performs the channel check on the continuous composite sampler.

These responsibilities are sul!ject to change without revision to this document.

Information PMP-6010-OSD-001 I Rev. 27 PaQe 60 of 92 OFF-SITE DOSE CALCULATION MANUAL Pages:

Attachment 3.4 Radioactive Gaseous Effluent Monitoring Instrumentation 60- 62 Instrument (Instrument#) Operable 1 Minimum Action Channels Action

1. Condenser Evacuation System

a. Mirian Noble Gas Activity (1) **** 6 Monitor (SRA-1905-A/1905-B and SRA-2905-A/2905-B)

b. Mirian Flow Rate Monitor (SFR-401 and (1) **** 5 PPC/RadServe SJAE display point) OR (SFR-402 and U1/U2 PPC/RadServe SJAE display point)

2. Unit Vent. Auxiliary Building Ventilation System

a. Mirian Noble Gas Activity (1)

• 6 Monitor (VRS-1505-A/1505-B and VRS-2505-A/2505-B)

b. Iodine Sampler (1)

• 8 Cartridge for VRA-1503/2503 C. Particulate Sampler Filter (1)

• 8 for VRA-1501 /2501

d. Mirian Effluent System Flow Rate (1)

• 5 Measuring Device (VFR-315 and U1/U2 PPC/RadServe VAB display point VFR-1510/2510)

e. Sampler Flow Rate (1) *# 5 Measuring Device (U1/U2 PPC/RadServe VAB display point PP-1500/2500) OR (VRS-1500/2500 local display)

3. Containment Purge and Containment Pressure Relief(Vent) **

a. Containment Noble Gas Activity Monitor (1) ****2.3 7 ERS-1305/1405 (ERS-2305/2405)

b. Containment Particulate Sampler Filter (1) **** 10 ERS-1301/1401 (ERS-2301/2401)

4. Waste Gas Holdup System and eves HUT (Batch releases)**

a. Mirian Noble Gas Activity (1) ****4 9 Alarm and Termination of Waste Gas Releases (VRS-1505-A/1505-B and VRS-2505-A/2505-B)

5. Gland Seal Exhaust

a. Noble Gas Activity (1) **** 6 Monitor (SRA-1805/2805)

b. Mirian Flow Rate Monitor (SFR-201 and (1) **** 5 U1/U2 PPC/RadServe GSLO display point)

OR (SFR-201 and SFR-1810/2810 local display)

Information PMP-6010-OSO-001 I Rev. 27 Page 61 of 92 OFF-SITE DOSE CALCULATION MANUAL Pages:

Attachment 3 .4 Radioactive Gaseous Effluent Monitoring Instrumentation 60- 62

• At all times

• • Containment Purge and other identified gaseous batch releases can be released utilizing the same double sampling compensatory action requirements of action 9 identified here even if there is no termination function associated with it like that associated with the two specific tank types listed here.

• • • • During releases via this pathway

1. . Unit 1/2 Channel 7: VFS-1525A, Channel 27: VFS-1521B, Channel 8: VFS-1525C TABLE NOTATIONS

1. IF an RMS monitor is INOPERABLE solely as the result of the loss of its control room alarm annunciation, THEN one of the following actions is acceptable to satisfy the ODCM action statement compensatory surveillance requirement:

1. Take grab samples and conduct laboratory analyses per the specific monitor's action statement,

-OR-

2. Take local monitor readings at a frequency equal to or greater than (more frequently than) the action frequency.

IF the RMS monitor is inoperable for reasons other than the loss of control room annunciation, TH EN the only acceptable action is taking grab samples and conducting laboratory analyses as the reading is equivalent to a grab sample when the monitor is functional.

With the Mirion RMS Upgrades, it is intended that an OPERABLE instrument/channel listed in the ODCM has both an operable transmitter and an operable display point, which may be local to the skid or on the PPC/RadServe system. This is in addition to control room annunciation function, if applicable.

2. Consider releases as occurring "via this pathway" under the following three conditions:

• The Containment Purge System is in operation and Containment Operability is applicable,

-OR-

• The Containment Purge System is in operation and the 'Clean-up' batch release of the Containment air volume has not been fully completed.

Note: IF neither of the above are applicable AND the unit is in Mode 5 or 6, THEN the containment purge system is acting as a ventilation system (an extension of the Auxiliary Building) and is covered by Item 2 of this Attachment. This is called 'Ventilation Mode'. 'Ventilate Mode' cannot be entered without performing a Clean-up batch release .

-OR-

• A Containment Pressure Relief (CPR) is being performed.

Once the 'Clean-up' batch release has been completed and 'Ventilation' mode of Purge has commenced - resultant return to 'Clean-up' mode can be made with no additional sampling requirements or paperwork - so long as either ERS-1305/2305 OR ERS-1405/2405 are operable. Containment particulate channels are not needed once the RCS has entered Mode 5 per Technical Specification 3.4 .15.

3. For purge (including pressure relief) purposes only. Reference TS 3.3.6, Containment Purge Supply and Exhaust System Isolation Instrumentation and 3.4.15, RCS Leakage Detection Instrumentation for additional information.

4. For waste gas releases only, see Item 2 (Unit Vent. Auxiliary Building Ventilation System) for additional requirements.

Information PMP-601 0-OSD-001 I Rev. 27 Pa~e 62 of 92 OFF-SITE DOSE CALCULATION MANUAL Pages:

Attachment 3.4 Radioactive Gaseous Effluent Monitoring Instrumentation 60- 62 ACTIONS

5. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. After 30 days, IF the channels are not OPERABLE, THEN continue releases with estimation of the flow rate once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and provide a description of why the inoperability was not corrected in the next Annual Radiological Effluent Release Report.

6. With the number of channels OPERABLE less required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per shift and these samples are analyzed for gross activity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. After 30 days, IF the channels are not OPERABLE, THEN continue releases with grab samples once per shift and provide a description of why the inoperability was not corrected in the next Annual Radiological Effluent release Report.

7. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirements, immediately suspend PURGING or VENTING (CPR) of radioactive effluents via this pathway.

8. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 30 days provided samples required for weekly Iodine & Particulates analysis are continuously collected with auxiliary sampling equipment as required in Attachment 3. 7, Radioactive Gaseous Waste Sampling and Analysis Program. After 30 days, IF the channels are not OPERABLE, THEN continue releases with sample collection by auxiliary sampling equipment and provide a description of why the inoperability was not corrected in the next Annual Radiological Effluent Release Report.

Sampling evolutions are not an interruption of a continuous release or sampling period.

9. With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank(s) may be released to the environment for up to 14 days provided that prior to initiating the release:

a. At least two independent samples (taken at a different times) of the tank's contents are analyzed and,

b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge valve lineups; otherwise, suspend release of radioactive effluents via this pathway.

After 14 days, IF the channels are not OPERABLE, THEN continue releases with sample collection by auxiliary sampling equipment and provide a description of why the inoperability was not corrected in the next Annual Radiological Effluent Release Report

10. Technical Specification 3.4.15, RCS Leakage Detection System Instrumentation.

Compensatory actions are governed by PMP-4030-EIS-001, Event-Initiated Surveillance Testing.

Information PMP-601 0-OSD-001 I Rev. 27 PaQe 63 of 92 OFF-SITE DOSE CALCULATION MANUAL Radioactive Gaseous Effluent Monitoring Pages:

Attachment 3.5 Instrumentation Surveillance Requirements 63 - 64 Instrument CHANNEL SOURCE CHANNEL CHANNEL OPERATIONAL CHECK CHECK I CALIBRATION TEST

1. Condenser Evacuation Alarm Only System

a. Mirian Noble Gas Activity D** M 8(2) 0(1)

Monitor (SRA-1905-A/ 1905-B, SRA-2905-A/ 2905-B)

b. Mirian System Effluent Flow D** NA B 0 Rate (SFR-401, SFR-402, U1/U2 PPC/RadServe SJAE display point , SRA-1910/2910)

2. Auxiliary Building Unit Alarm Only Ventilation System

a. Mirian Noble Gas Activity D* M 8(2) 0(1)

Monitor (VRS-1505-A/ 1505-B and VRS-2505-A/ 2505-B)

b. Iodine Sampler W* NA NA NA (For VRA-1503/2503)

c. Particulate Sampler W* NA NA NA (For VRA-1501/2501)

d. Mirian System Effluent Flow D* NA B 0 Rate Measurement Device (VFR-315, U1/U2 PPC/RadServe V AB display point, VRS-1510/2510)

e. Mirian Sampler Flow Rate D* N/A B 0 Measuring Device (U1/U2 PPC/RadServe VAB display point PP-1500/2500 or local display)

3. Containment Purge System and Alarm and Trip Containment Pressure Relief

a. Containment Noble Gas s p 8(2) 0 Activity Monitor (ERS-13/1405 and ERS-23/2405)

b. Containment Particulate s NA B 0 Sampler (ERS-13/1401 and ERS-23/2401)

4. Waste Gas Holdup System Alarm and Trip Including CVCS HUT

a. Mirian Noble Gas Activity p p 8(2) 0(3)

Monitor Providing Alarm and Termination (VRS-1505-A/1505-B and VRS-2505-A/2505-8)

Information PMP-601 0-OSD-001 I Rev. 27 Paqe 64 of 92 OFF-SITE DOSE CALCULATION MANUAL Radioactive Gaseous Effluent Monitoring Pages:

Attachment 3.5 Instrumentation Surveillance Requirements 63 - 64 Instrument

5. Gland Seal Exhaust CHANNEL CHECK Alarm Only SOURCE CHECK I CHANNEL CALIBRATION CHANNEL OPERATIONAL TEST

a. Mirion Noble Gas Activity D** M 8(2) 0(1)

(SRA-1805/2805)

b. System Effluent Flow Rate D** NA B Q (SFR-201, U1/U2 PPC/RadServe GSLO display point, SRA-1810/2810)

• At all times

• • During releases via this pathway. This is applicable to all surveillances for the appropriate monitor.

TABLE NOTAT IONS

1. Demonstrate with the CHANNEL OPERATIONAL TEST that control room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm setpoint.

2. Circuit failure.

3. Instrument indicates a downscale failure .

4. Instrument controls not set in operate mode.

2. Perform the initial CHANNEL CALIBRATION using one or more sources with traceability back to the NIST.

These sources permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration may be used .

3. Demonstrate with the CHANNEL OPERATIONAL TEST that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm/trip setpoint.

2. Circuit fa ilure.*

3. Instrument indicates a downscale failure .*

4. Instrument controls not set in operate mode.*

• Instrument indicates, but does not provide automatic isolation.

Operations currently performs the routine channel checks, and source checks. Maintenance and Radiation Protection perform channel calibrations and channel operational tests. These responsibilities are su~ect to change without revision to this document.

Rest of this page intentionally blank

Information PMP-6010-OSD-001 I Rev. 27 I Page 65 of 92 OFF-SITE DOSE CALCULATION MANUAL Pages:

Attachment 3.6 Radioactive Liquid Waste Sampling and Analysis Program 65 - 66

[Ref. 5.2.1r]

LIQUID SAMPLING MINIMUM TYPE OF LOWER RELEASE FREQUENCY ANALYSIS ACTIVITY LIMIT OF TYPE FREQUENCY ANALYSIS DETECTION (LLD)

(µCi/ml) a A. Batch Waste p p Principal 5x10* 7 Release Tanks c Each Batch Each Batch Gamma Emitters e 1-131 1x10*6 p p Dissolved and Entrained Gases Each Batch Each Batch (Gamma 1x10*5 Emitters) p M H-3 1x10*5 Each Batch Compositeb Gross Alpha 1x10*7 p Q Sr-89, Sr-90 5x10*8 Each Batch Compositeb Fe-55 1x10*6 B. Plant w Principal Continuous Daily Compositeb Gamma 5x10* 7 Releases* d Emitters e 1-131 1x10*6 M M Dissolved and Grab Sample Entrained Gases 1x10*5 (Gamma Emitters)

M H-3 1x10*5 Daily Compositeb Gross Alpha 1x10*7 Q Sr-89, Sr-90 5x10*8 Daily Compositeb Fe-55 1x10*6

• During releases via this pathway This table provides the minimum requirements for the liquid sampling program. If additional sampling is performed then those sample results can be used to quantify releases in lieu of composite data for a more accurate quantification. Examples of these samples are the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> secondary coolant activity and Monitor Tank tritium samples.

Information PMP-601 0-OSD-001 I Rev. 27 I PaQe 66 of 92 OFF-SITE DOSE CALCULATION MANUAL Pages:

Attachment 3.6 Radioactive Liquid Waste Sampling and Analysis Program 65 - 66 TABLE NOTATION

a. The lower limit of detection (LLD) is defined in Table Notation A. of Attachment 3.20, Maximum Values for Lower Limits of Detections A,B - REMP

b. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released .

c. A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analysis, isolate and ensure thorough mixing (recirculate, sparge, etc) for each batch. Examples of these are Monitor Tank and Steam Generator Drains. Before a batch is released the tank is sampled and analyzed to determine that it can be released without exceeding federal standards.

d. A continuous release is the discharge of liquid of a non-discrete volume; e.g. from a volume of system that has an input flow during the continuous release. This type of release includes the Turbine Room Sump, Steam Generator Slowdown and the Steam Generator Sampling System.

e. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 .

This list does not mean that only these nuclides are to be detected and reported. Identify and report other peaks, which are measurable and identifiable, together with the above nuclides.

Information PMP-601 0-OSD-001 I Rev. 27 Paoe 67 of 92 OFF-SITE DOSE CALCULATION MANUAL Radioactive Gaseous Waste Sampling and Pages:

Attachment 3. 7 Analysis Program 67 -68 Gaseous Release Type Frequency Minimum Type of Lower Limit Analysis Activity of Detection Frequency Analysis (µCi/cc) a

a. Waste Gas Storage p p Principal Gamma Tanks and CVCS HUTs Each Tank Each Tank Emittersd 1 X 10*4 Grab Sample H-3 1 X 10*6

b. Containment Purge p p Principal Gamma Each Purge Each Purge Emitters d 1 X 10*4 Grab Sample .

CPR (vent)** Twice per Twice per Month Month H-3 1 X 10*6 C. Condenser Evacuation WorM M Principal Gamma System Grab Sample Particulate Sample Emittersd 1 X 10*11 Gland Seal Exhaust* i H-3 1 X 10*6 M

W9 Principle Gamma 1 X 10*4 Noble Gas Emitters d M 1-131 Iodine Adsorbing 1 X 10*12 Media Continuous W9 Noble Gases Noble Gas Monitor 1X ,0* 6

d. Auxiliary Building Unit Continuous c Wb 1-131 Vent* Iodine Adsorbing 1 X 10*12 Media Continuous c Wb Principal Gamma Particulate Sample Emittersd 1 X 10*11 Continuous c M Gross Alpha Composite Particulate 1X ,0-11 Sample w Wh H-3 Grab Sample H-3 Sample 1 X 10*6 W9J Principle Gamma 1 X 10*4 Noble Gas Emitters d Continuous c Q Sr-89, Sr-90 Composite Particulate 1 X 10*11 Sample Continuous c Noble Gas Monitor Noble Gases 1 X 10*6

e. Incinerated Oil e p p Principal Gamma Each Batch r Each Batchr Emittersd 5 X 10*7

• During releases via this pathway

• • Only a twice per month sampling program for containment noble gases and H3 is required This table provides the minimum requirements for the gaseous sampling program . If additional sampling is performed then those sample results can be used to quantify releases in lieu of composite data for a more accurate quantification.

Examples of these samples are verification or compensatory action sample results.

Information PMP-601 0-OSD-001 I Rev. 27 PaQe 68 of 92 OFF-SITE DOSE CALCULATION MANUAL Radioactive Gaseous Waste Sampling and Pages:

Attachment 3.7 Analysis Program 67 - 68 TABLE NOTATION

a. The lower limit of detection (LLD) is defined in Table Notation A. of Attachment 3.20, Maximum Values for Lower Limits of Detections A,B - REMP

b. Change samples at least once per 7 days and complete analyses within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing.

Perform analyses at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for 7 days following each shutdown, startup or THERMAL POWER change greater than 15% per hour of RATED THERMAL POWER. WHEN samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, THEN the corresponding LLDs may be increased by a factor of

10. This requirement does not apply IF (1) analysis shows that DOSEQ 1131 concentration in the RCS has not increased more than a factor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3. IF the daily sample requirement has been entered, THEN it can be exited early once both the radiation monitor reading and the RCS DOSEQ 1131 levels have returned to within the factor of 3 of the pre-event 'normal' .[Ref. 5.2.1x]

c. Know the ratio of the sample flow rate to the sampled stream flow rate for the time period covered by each dose or dose rate calculation made in accordance with steps 3.2.4a, 3.2.4b, and 3.2 .4c of this document.

Sampling evolutions or momentary interruptions to maintain sampling capability are not an interruption of a continuous release or sampling period.

d. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133M, Xe-135 and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported . Identify and report other peaks, which are measurable and identifiable, together with the above nuclides.

e. Releases from incinerated radioactive oil are discharged through the Auxiliary Boiler System. Account for releases based on pre-release grab sample data.

f. Collect samples of waste oil to be incinerated from the container in which the waste oil is stored (example: waste oil storage tanks, 55 gal. drums) prior to transfer to the Auxiliary Boiler System.

Ensure samples are representative of container contents.

g. Obtain and analyze a gas marinelli grab sample weekly for noble gases effluent quantification.

h. Take tritium grab samples at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling cavity is flooded .

i. Grab sampling of the Gland Seal Exhaust pathway need not be performed if the RMS low range channel readings are less than 1E-6 µC/cc. Attach the RMS daily averages in lieu of sampling. This is based on operating experience indicating no activity is detected in the Gland Seal Exhaust below this value. Compensatory sampling for out of service monitor is still required in the event the detector is inoperable.

j. Sampling and analysis shall also be performed following shutdown, startup or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a one hour period. This noble gas sample shall be performed within four hours of the event. Evaluation of the sample results, based on previous samples, will be performed to determine if any further sampling is necessary.

Information PMP-601 0-OSD-001 I Rev. 27 Paoe 69 of 92 OFF-SITE DOSE CALCULATION MANUAL Page:

Attachment 3.8 Multiple Release Point Factors for Release Points 69 Liquid Factors Monitor Description Monitor Number MRP#

U 1 SG Slowdown 1-DRA-300, 1-DRA-353 0.35 U 2 SG Slowdown 2-DRA-300, 2-DRA-353 0.35 U 1 & 2 Liquid Waste Discharge RRS-1001-A, RRS-1021-B 0.30 Sources of radioactivity released from the Turbine Room Sump (TRS) typically originate from the secondary cycle which is already being monitored by instrumentation that utilizes multiple release point (MRP) factors. The MRP is an administrative value that is used to assist with maintaining releases ALARA. The TRS has no actual radiation monitor, but utilizes an automatic compositor for monitoring what has been released. The batch release path, through RRS-1001-A/ 1021-B, is the predominant release path by several magnitudes. Tritium is the predominant radionuclide released from the site and the radiation monitors do not respond to this low energy beta emitter. Based on this information and the large degree of conservatism built into the radiation monitor setpoint methodology it does not appear to warrant further reduction for the TRS release path since its source is predominantly the secondary cycle which is adequately covered by this factor.

Gaseous Factors Monitor Description Monitor Number Flow Rate (cfm) MRP#

Unit 1 Unit Vent VRS-1500 186,600 0.54 Gland Seal Vent SRA-1800 1,260 0.00363 Steam Jet Air Ejector SRA-1900 3,600 (b) 0.01 Start Up FT Vent 1,536 0.004 Total 192,996 Unit 2 Unit Vent VRS-2500 143,400 0.41 Gland Seal Vent SRA-2800 5,508 (a) 0.02 Steam Jet Air Ejector SRA-2900 3,600 (b) 0.01 Start Up FT Vent 1,536 0.004 Total 154,044

1. Nominal Values a Two release points of 2,754 cfm each are totaled for this value.

b This is the total design maximum of the Start Up Air Ejectors. This is a conservative value for unit 1.

Information PMP-601 0-OSD-001 I Rev. 27 PaQe 70 of 92 OFF-SITE DOSE CALCULATION MANUAL Page:

Attachment 3. 9 Liquid Effluent Release Systems 70 sa.Rl:5 SYSTEM5 ClrtyV\bus:

AoorOrains. StationOrain(Oirty) Oean5Ufl1)

OecorUmination 5'.n1>Tri Tank Ri~Solutlons, OlemcalOrain Tank, Be.

W,,,eHQjd~ Tank (Oean)

Oaan'Veaes:

Fq\>pmerd Orains.

Pun-c>Seal w.aelt:ll~Tank Leakoff~ (Oirl)

Contairvnent Fan Oretiating Cooler Olerncal Drain Tank 1~yHo1S-1 Wiler Condensale.Bc. ~ris(2) Clscharge O.CSBoricacid

&aporator Package,. North BaiccAcidEvaporation t"7 Evaporator Condensate Oenineralizer andSculh Steam SleamGoierator Generator Bl...townand Bl...town Trealmert System f-----* 0::lng (Potential)

Screent-bJ!lo Oisr::haroe

&,e,'\lial Service VlblerSysaem (Potential) l5an'4>1*Point CircUd:ingWtter Intake Pipes

• I Cor1aiMlMISp"f ~---.i*~. . __.I________.,.,

_ Heat ExchMgers . ~

Orcutas irg Wiler Clscharge TwbineRoom AawMoter Surr!)lhl 1 and2

{Potential) eon.,o,ite

~

8 .S71'&.nl> 14'---,------ -----------------t pHMeter Orculat,ng L----- - - -- -- - -- -- - -- - - - -- --4 Screentb.m 1---..,.. WIier Ois:harge

Information PMP-601 O-OSD-001 I Rev. 27 Paoe 71 of 92 OFF-SITE DOSE CALCULATION MANUAL Page:

Attachment 3.10 Plant Liquid Effluent Parameters 71 SYSTEM COMPONENTS CAPACITY FLOW RATE TANKS I PUMPS (EACH) (EACH)*

I Waste Disposal System

+ Chemical Drain Tank 1 1 600 GAL. 20 GPM

+ Laundry & Hot Shower Tanks 2 1 600 GAL. 20 GPM

+ Monitor Tanks 4 2 21,600 GAL. 150 GPM

+ Waste Holdup Tanks 2 25,000 GAL.

+ Waste Evaporators 3 30 GPM

+ Waste Evaporator Condensate 2 2 6,450 GAL 150 GPM Tanks 11 Steam Generator Slowdown and Slowdown Treatment Systems

+ Start-up Flash Tank (Vented)# 1 1,800 GAL. 580 GPM

+ Normal Flash Tank (Not 1 525 GAL. 100 GPM Vented)

+ Slowdown Treatment System 1 60 GPM 111 Essential Service Water System

+ Water Pumps 4 10,000 GPM

+ Containment Spray Heat 4 3,300 GPM Exchanger Outlet IV Circulating Water Pumps I Unit 1 Unit 2 3

4 230,000 GPM 230,000 GPM

• Nominal Values

1. The 580 gpm value is calculated from the Estimated Steam Generator Slowdown Flow vs . DRV Valve Position letter prepared by M. J. O'Keefe, dated 9/27/93 . This is 830 gpm times the 70% that remains as liquid while the other 30% flashes to steam and exhausts out the flash tank vent.

Information PMP-601 0-OSD-001 I Rev. 27 I PaQe 72 of 92 OFF-SITE DOSE CALCULATION MANUAL Volumetric Detection Efficiencies for Principle Gamma Pages: .11 Emitting Radionuclides for Mirion Liquid Monitors 72 Mirion RRS-1001A/ 1021B Detection Detection efficiency efficiency

{cpm/(

Nuclide {cps/(Bq/m3)}

µCi/cc)}

Ag-108m 7.22E-04 1.60E+09 Ag-110m 8.45E-04 1.88E+09 Ba-137m 2.42E-04 5.37E+08 Ce-144 1.01 E-05 2.24E+07 Co-57 6.78E-05 1.51E+08 Co-58 3.38E-04 7.50E+08 Co-60 4.99E-04 1.11E+09 Cr-51 2.47E-05 5.48E+07 Cs-134 5.92E-04 1.31 E+09 Cs-137 2.27E-04 5.04E+08 Fe-55 9.91E-14 2.20E-01 Fe-59 2.62E-04 5.82E+08 1-131 2.SOE-04 5.55E+08 1-133 2.71E-04 6.02E+08 ln-113m 1.71 E-04 3.80E+08 Kr-85 1.15E-06 2.55E+06 Mn-54 2.67E-04 5.93E+08 Mo-99 1.53E-04 3.40E+08 Na-24 4.23E-04 9.39E+08 Nb-95 2.66E-04 5.91E+08 Pr-144 5.93E-06 1.32E+07 Sb-122 2.02E-04 4.48E+08 Sb-124 4.75E-04 1.05E+09 Sb-125 2.23E-04 4.95E+08 Sn-113 1.75E-04 3.89E+08 Sn-117m 1.19E-04 2.64E+08 Tc-99m 9.10E-05 2.02E+08 Xe-131m 2.84E-06 6.30E+06 Xe-133 1.32E-07 2.93E+05 Xe-133m 2.19E-05 4.86E+07 Xe-135 2.0SE-04 4.62E+08 Zn-65 1.33E-04 2.95E+08 Zr-95 2.66E-04 5.91E+08 Bq=Becquerel Note: 1 cps/(Bq/m3) = 2.22e+12 cpm/(µCi/cc)

Information PMP-601 0-OSD-001 I Rev . 27 I Paqe 73 of 92 OFF-SITE DOSE CALCULATION MANUAL Pages: .12 Counting Efficiency for l/2-DRA-300 and l/2-DRA-353 73 - 74 Mirian l/2-DRA-300 4n Shield Detection Detection efficiency efficiency Nuclide {cps/(Bq/m3)} {cpm/( µCi/cc)}

Mn-54 3.37E-06 7.48E+06 Co-58 4 .45E-06 9.88E+06 Co-60 6.69E-06 1.49E+07 Cs-137 2 .90E-06 6 .44E+06 1-131 3.63E-06 8 .06E+06 1-132 1.00E-05 2.22E+07 1-133 3.61E-06 8.01E+06 1- 134 1.03E-05 2 .29E+07 I- 135D 8.89E-06 1.97E+07

{based on actual pre-installation counting performed with an iodine source term)

Bq = Becquerel Note: 1 cps/(Bq/m3) = 2.22e+ 12 cpm/(µCi/cc) 41t Shield = shielding encompasses the detector and the sample piping per design criteria Mirian Detectors 1/2-DRA-300 replaced the R-19 and DRS-3100/4100 detectors

Information PMP-601 0-OSD-001 I Rev . 27 I PaQe 74 of 92 OFF-SITE DOSE CALCULATION MANUAL Pages: .12 Counting Efficiency for l/2-DRA-300 and l/2-DRA-353 73 - 74 Mirion l/2-DRA-353 4n Shield Detection Detection efficiency efficiency Nuclide (cps/ (Bq/ ml>> {cpm/( 1,1Ci/cc)}

Mn-54 1.09E-05 2.42E+07 Co-58 1.43E-05 3.17E+07 Co-60 2.20E-05 4.88E+07 Cs-137 9.31E-06 2.07E+07 1-131 l .05E-05 2.33E+07 1-132 3.22E-05 7.15E+07 1-133 l.13E-05 2.51E+07 1- 134 3.29E-05 7.30E+07 1-1350 2.55E-05 5.66E+07 (based on actual pre-installation counting performed with an iodine source term)

Bq = Becquerel Note: 1 cps/(Bq/m3) = 2.22e+ 12 cpm/(µCi/cc) 41t Shield= shielding encompasses the detector and the sample piping per design criteria Mirian Detectors 1/2-DRA-353 replaced the R-24 and DRS-3200/4200 detectors

Information PMP-6010-OSD-001 I Rev. 27 I Paqe 75 of 92 OFF-SITE DOSE CALCULATION MANUAL Pages:

Attachment 3.13 Counting Efficiency for l-WRA-713, 2-WRA-714, 1-WRA-717, and 2-WRA-718 75-76 Mirian 1-WRA713, 2-WRA-714 Mirian 1-WRA713, 2-WRA-714 Mirian 1-WRA713, 2-WRA-714 Detection Detection Detection Detection Detection Detection efficiency efficiency efficiency efficiency efficiency efficiency Nuclide {cps/(Bq/m3)} {cpm/( l,ICi/cc)} Nuclide {cps/(Bq/m3)} {cpm/( l,ICi/cc)}

Nuclide { cps/(Bq/m3)} {cpm/( l,ICi/cc)}

Kr-88 4.04E-06 8.97E+06 Sb-129 5.56E-06 1.23E+07 Am-241 4.81E-10 1.07E+03 La-140 6.SOE-06 1.44E+07 Sr-89 2.89E-10 6.42E+02 Ba-137m 2.79E-06 6.19E+06 La-141 5.68E-08 1.26E+05 Sr-91 4.SSE-06 1.01 E+07 Ba-139 8.02E-07 1.78E+06 La-142 4.43E-06 9.83E+06 Sr-92 3.02E-06 6.70E+06 Ba-140 1.31E-06 2.91E+06 Mo-99 3.25E-06 7.22E+06 Tc-99m 2.37E-06 5.26E+06 Ce-141 1.34E-06 2.97E+06 Nb-95 3.08E-06 6.84E+06 Te-127 4.25E-08 9.44E+04 Ce-143 2.18E-06 4.84E+06 Nd-147 7.0?E-07 1.57E+06 Te-127m 5.49E-10 1.22E+03 Ce-144 2.54E-07 5.64E+05 Np-239 1.90E-06 4.22E+06 Te-129 3.87E-07 8.59E+05 Cm-242 7.56E-11 1.68E+02 Pr-143 3.78E-14 8.39E-02 Te-129m 1.32E-07 2.93E+05 Cm-244 5.06E-11 1.12E+02 Pr-144 7.41 E-08 1.65E+05 Te-131m 6.53E-06 1.45E+07 Cs-134 7.26E-06 1.61E+07 Pu-238 6.62E-11 1.47E+02 Te-132 3.25E-06 7.22E+06 Cs-136 8.68E-06 1.93E+07 Pu-239 4.97E-10 1.10E+03 Xe-133 3.42E-09 7.59E+03 Cs-137 2.63E-06 5.84E+06 Pu-240 6.93E-11 1.54E+02 Xe-135 3.37E-06 7.48E+06 1-131 3.45E-06 7.66E+06 Pu-241 1.18E-11 2.62E+01 Y-90 3.83E-14 8.SOE-02 1-132 9.53E-06 2.12E+07 Rb-86 2.56E-07 5.68E+05 Y-91 7.49E-09 1.66E+04 1-133 3.35E-06 7.44E+06 Rh-103m O.OOE+OO O.OOE+OO Y-92 8.13E-07 1.80E+06 1-134 9.04E-06 2.01E+07 Rh-105 8.74E-07 1.94E+06 Y-93 4.56E-07 1.01E+06 I-135D 8.02E-06 1.78E+07 Rh-106 1.08E-06 2.40E+06 Zr-95 3.11E-06 6.90E+06 Kr-85 1.39E-08 3.09E+04 Ru-103 3.13E-06 6.95E+06 Zr-97 3.82E-06 8.48E+06 Kr-85m 2.81 E-06 6.24E+06 Ru-105 4.22E-06 9.37E+06 Kr-87 2.68E-06 5.95E+06 Sb-127 3.82E-06 8.48E+06 Bq = Becquerel Note: 1 cps/(Bq/m3) = 2.22e+ 12 cpm/(µCi/cc)

Information PMP-601 0-OSD-001 I Rev. 27 I Page 76 of 92 OFF-SITE DOSE CALCULATION MANUAL Pages:

Attachment 3.13 Counting Efficiency for l-WRA-713, 2-WRA-714, 1-WRA-717, and 2-WRA-718 75-76 Mirian 1-WRA-717, 2-WRA-718 Detection Detection Mirian 1-WRA-717, 2-WRA-718 Mirian 1-WRA-717, 2-WRA-718 efficiency efficiency Detection Detection Detection Detection Nuclide {cps/(Bq/m3)} {cpm/( µCi/cc)} efficiency efficiency efficiency efficiency Am-241 7.29E-10 1.62E+03 Nuclide {cps/(Bq/m3)} {cpm/( pCi/cc)} Nuclide {cps/(Bq/m3)} {cpm/( µCi/cc)}

Ba-137m 1.71 E-05 3.80E+07 Kr-88 2.45E-05 5.44E+07 Sb-129 3.56E-05 7.90E+07 Ba-139 1.47E-06 3.26E+06 La-140 4.13E-05 9.17E+07 Sr-89 1.93E-09 4.28E+03 Ba-140 6.64E-06 1.47E+07 La-141 4.33E-07 9.61E+05 Sr-91 2.85E-05 6.33E+07 Ce-141 1.85E-06 4.11E+06 La-142 2.90E-05 6.44E+07 Sr-92 2.20E-05 4.88E+07 Ce-143 9.67E-06 2.15E+07 Mo-99 7.11E-06 1.58E+07 Tc-99m 2.95E-06 6.55E+06 Ce-144 2.90E-07 6.44E+05 Nb-95 1.98E-05 4.40E+07 Te-127 2.08E-07 4.62E+05 Cm-242 1.38E-10 3.06E+02 Nd-147 3.34E-06 7.41E+06 Te-127m 3.25E-09 7.22E+03 Cm-244 1.15E-10 2.55E+02 Np-239 4.80E-06 1.07E+07 Te-129 2.0SE-06 4.55E+06 Cs-134 4.33E-05 9.61E+07 Pr-143 2.40E-13 5.33E-01 Te-129m 7.88E-07 1.75E+06 Cs-136 5.19E-05 1.15E+08 Pr-144 4.93E-07 1.09E+06 Te-131m 3.SSE-05 7.88E+07 Cs-137 1.67E-05 3.71E+07 Pu-238 6.08E-11 1.35E+02 Te-132 9.88E-06 2.19E+07 1-131 1.59E-05 3.53E+07 Pu-239 1.46E-09 3.24E+03 Xe-133 4.99E-09 1.11E+04 1-132 5.72E-05 1.27E+08 Pu-240 5.84E-11 1.30E+02 Xe-135 1.25E-05 2.78E+07 1-133 1.95E-05 4.33E+07 Pu-241 1.17E-11 2.60E+01 Y-90 3.01 E-13 6.68E-01 1-134 6.14E-05 1.36E+08 Rb-86 1.78E-06 3.95E+06 Y-91 5.46E-08 1.21E+05 1-135D 4.15E-05 9.21E+07 Rb-103m 0.00E+00 0.00E+00 Y-92 5.51E-06 1.22E+07 Kr-85 7.94E-08 1.76E+05 Rh -10 5 3.54E-06 7.86E+06 Y-93 2.19E-06 4.86E+06 Kr-85m 5.53E-06 1.23E+07 Rh -106 6.25E-06 1.39E+07 Zr-95 1.90E-05 4.22E+07 Kr-87 1.SSE-05 3.44E+07 Ru-103 1.74E-05 3.86E+07 Zr-97 2.36E-05 5.24E+07 Ru -10 5 2.23E-05 4.95E+07 Sb-127 2.07E-05 4.60E+07 Bq = Becquerel Note: 1 cps/(Bq/m3) = 2.22e+ 12 cpm/(µCi/cc)

Information PMP-601 0-OSD-001 I Rev. 27 Paqe 77 of 92 OFF-SITE DOSE CALCULATION MANUAL Page:

Attachment 3.14 Gaseous Effluent Release Systems 77 RB.EASE SOURCES SYSTEMS POINTS Waste Gas Decay Vent Header Tanks and eves HUT Moisture Gas Decay Flow Isolat ion Separator Tanks t

eves Re ulator Valve Aux.BuildingVent * ~ - - - - - , . HUT From Areas and Rooms FeaturesVent System Engineered Pre HEPA Safety Features Enclosures Vent and Pipe Shaft Filter Filler

• ,c

{:.

Fuel Handling Ventilation E

C Q) a:

Contai nment Conta i nment Purge and Re lief Purge System Conta inment Reli ef Instrument Room Plant Vent Purge System Instrumentat ion lo Room atmosphere AlrborneLOWOt Con1alnm,n1 Radiation Upper Conlahvncn1 Area Monitors Thesoisot

• tocont

• 1""1ilfll Radl

• 1lonMonl1or This Conta1nment 1---------------.....i,!.,S=*=m=p=lin=g=P=o=;"='=-J....--il! lnst~:~:,::.::~1~:'hl- 1.ot

• tes c<<11

• Jm1>N r

• purgo,ctm rollof,and 1

---

~====="="=m=====-l

• x~:::s=~hO::,nt Local Steam Generator S lowdown Startup Flash Tank Silencer L-----'

1--------------------------------~ Exhaust to atmosphere Treatment System Normal To Treatment System

• Flash Tank no gaseousrelease ondenser A ir E;ector System  ! I Steam Jet Air

~------------,

Radiation FlowDola Flow Monitor I Sampling Point 1-'-----------------------------.i Local Exhaust to actors atmosphere Gland Seal Condenser UL Sampling

)~! Pro-

,_,_ _..-_-_-_~..,lo

~~~_ L___ i Local Exhaust rs:;:;;;;;;,;;;:;;;;;;;--1------------l-Steam Packing Radiation ,--Fl-ow~M-on-;-,o-,--,1-----------------M ExhauSl to

&hauster atmosphere

Information PMP-601 0-OSD-001 I Rev. 27 PaQe 78 of 92 OFF-SITE DOSE CALCULATION MANUAL Page:

Attachment 3.15 Plant Gaseous Effluent Parameters 78 SYSTEM UNIT EXHAUST CAPACITY FLOW RATE (CFM)

I PLANT AUXILIARY BUILDING 1 186,600 max UNIT VENT 2 143,400 max WASTE GAS DECAY TANKS (8) 1 125 4082 FP @100 psig AND CHEMICAL & VOLUME 28,741 ft 3 max CONTROL SYSTEM HOLD UP @ 8#, 0 level TANKS (3)

+ AUXILIARY BUILDING 1 72,660 EXHAUST 2 59,400

+ ENG. SAFETY FEATURES 1& 2 50,000 VENT

+ FUEL HANDLING AREA VENT 1 30,000 SYSTEM CONTAINMENT PURGE SYSTEM 1& 2 32,000 CONTAINMENT PRESSURE 1& 2 1,000 RELIEF SYSTEM INSTRUMENT ROOM PURGE 1& 2 1,000 SYSTEM II CONDENSER AIR EJECTOR 2 Release Points SYSTEM One for Each Unit NORMAL STEAM JET AIR 1& 2 230 EJECTORS START UP STEAM JET AIR 1& 2 3,600 EJECTORS 111 TURBINE SEALS SYSTEM 1 1,260 2 5,508 2 Release Points for Unit 2 IV START UP FLASH TANK VENT 1 1,536 2 1,536

+ Designates total flow for all fans .

Information PMP-601 0-OSD-001 I Rev . 27 PaQe 79 of 92 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.16 10 Year Average of 1995-2004 Data Pages: 79 - 80 x/Q GROUND AVERAGE (sec/m 3)

DIRECTION DISTANCE (METERS)

{WIND FROM) 594 2416 4020 5630 7240 N 4.17E-06 4.82E-07 2.25E-07 1.33E-07 9.32E-08 NNE 3.02E-06 3.64E-07 1.73E-07 1.04E-07 7.29E-08 NE 4.54E-06 5.31 E-07 2.60E-07 1.59E-07 1.13E-07 ENE 7.16E-06 7.99E-07 4.04E-07 2.52E-07 1.80E-07 E 1.04E-05 1.13E-06 5.82E-07 3.66E-07 2.63E-07 ESE 1.07E-05 1.18E-06 6.04E-07 3.78E-07 2.72E-07 SE 1.15E-05 1.24E-06 6.36E-07 4.00E-07 2.88E-07 SSE 1.30E-05 1.42E-06 7.27E-07 4.57E-07 3.29E-07 s 1.41E-05 1.57E-06 7.92E-07 4.93E-07 3.54E-07 SSW 7.03E-06 7.81 E-07 3.90E-07 2.41E-07 1.72E-07 SW 4.12E-06 4.73E-07 2.28E-07 1.38E-07 9.73E-08 WSW 3.29E-06 3.65E-07 1.76E-07 1.06E-07 7.52E-08 w 3.63E-06 4.11 E-07 1.96E-07 1.18E-07 8.31 E-08 WNW 3.02E-06 3.43E-07 1.61 E-07 9.59E-08 6.71E-08 NW 3.22E-06 3.61 E-07 1.71E-07 1.02E-07 7.16E-08 NNW 3.84E-06 4.29E-07 2.02E-07 1.20E-07 8.40E-08 DIRECTION DISTANCE (METERS)

(WIND FROM) 12067 24135 40225 56315 80500 N 4.64E-08 1. 79E-08 8.89E-09 5.68E-09 3.56E-09 NNE 3.66E-08 1.43E-08 7 .13E-09 4.56E-09 2.87E-09 NE 5.75E-08 2.30E-08 1.15E-08 7.41 E-09 4.72E-09 ENE 9.30E-08 3.80E-08 1.91E-08 1.23E-08 7.90E-09 E 1.37E-07 5.65E-08 2.85E-08 1.83E-08 1.18E-08 ESE 1.41E-07 5.81E-08 2.93E-08 1.88E-08 1.22E-08 SE 1.50E-07 6.20E-08 3.12E-08 2.01 E-08 1.30E-08 SSE 1.71E-07 7.06E-08 3.56E-08 2.29E-08 1.48E-08 s 1.84E-07 7.49E-08 3.77E-08 2.43E-08 1.56E-08 SSW 8.86E-08 3.59E-08 1.B0E-08 1.15E-08 7.39E-09 SW 4.93E-08 1.96E-08 9.77E-09 6.27E-09 3.98E-09 WSW 3.80E-08 1.51E-08 7.53E-09 4.83E-09 3.07E-09 w 4.17E-08 1.64E-08 8.13E-09 5.20E-09 3.28E-09 WNW 3.34E-08 1.29E-08 6.41 E-09 4.10E-09 2.57E-09 NW 3.57E-08 1.39E-08 6.89E-09 4.41 E-09 2.77E-09 NNW 4.19E-08 3.35E-08 8.10E-09 5.19E-09 3.27E-09 DIRECTION TO - SECTOR N = A E = E s = J w = N NNE = B ESE = F SSW = K WNW = p NE = C SE = G SW = L NW = Q ENE = D SSE = H WSW = M NNW = R Worst Case x/Q = 2.04E-05 sec/m 3 in Sector H 2004

Information PMP-601 0-OSD-001 I Rev. 27 Page 80 of 92 OFF-SITE DOSE CALCULATION MANUAL Attachment 3.16 10 Year Average of 1995-2004 Data Pages: 79- 80 D/Q DEPOSITION {1/m 2)

DISTANCE (METERS)

WIND FROM 594 2416 4020 5630 7240 N 2.37E-08 2.29E-09 1.04E-09 5.44E-10 3.47E-10 NNE 9.86E-09 9.52E-10 4.32E-10 2.27E-10 1.45E-10 NE 1.29E-08 1.25E-09 5.67E-10 2.97E-10 1.90E-10 ENE 1.59E-08 1.54E-09 6.97E-10 3.66E-10 2.33E-10 E 1.87E-08 1.81 E-09 8.20E-10 4.30E-10 2.75E-10 ESE 1.85E-08 1. 79E-09 8.12E-10 4.26E-10 2.72E-10 SE 1.90E-08 1.83E-09 8.30E-10 4.36E-10 2.78E-10 SSE 2.40E-08 2.32E-09 1.05E-09 5.52E-10 3.52E-10 s 3.68E-08 3.56E-09 1.61E-09 8.46E-10 5.40E-10 SSW 2.30E-08 2.22E-09 1.01 E-09 5.28E-10 3.37E-10 SW 2.22E-08 2.15E-09 9.74E-10 5.11E-10 3.26E-10 WSW 2.11 E-08 2.04E-09 9.23E-10 4.84E-10 3.09E-10 w 2.00E-08 1.93E-09 8.74E-10 4.59E-10 2.93E-10 WNW 1.75E-08 1.69E-09 7.64E-10 4.01E-10 2.56E-10 NW 1.58E-08 1.53E-09 6.94E-10 3.64E-10 2.32E-10 NNW 2.30E-08 2.22E-09 1.01 E-09 5.28E-10 3.37E-10 DIRECTION DISTANCE (METERS)

(WIND FROM 12067 24135 40225 56315 80500 N 1.45E-10 4.72E-11 1.74E-11 9.27E-12 4.65E-12 NNE 6.36E-11 1.97E-11 7.24E-12 3.86E-12 1.94E-12 NE 8.07E-11 2.58E-11 9.51 E-12 5.07E-12 2.54E-12 ENE 9.77E-11 3.17E-11 1.17E-11 6.23E-12 3.13E-12 E 1.14E-10 3.73E-11 1.37E-11 7.34E-12 3.68E-12 ESE 1.13E-10 3.70E-11 1.36E-11 7.26E-12 3.64E-12 SE 1.16E-10 3.78E-11 1.39E-11 7.42E-12 3.72E-12 SSE 1.47E-10 4.79E-11 1.76E-11 9.41E-12 4.72E-12 s 2.25E-10 7.34E-11 2.70E-11 1.44E-11 7.23E-12 SSW 1.41E-10 4.59E-11 1.69E-11 9.01E-12 4.52E-12 SW 1.36E-10 4.43E-11 1.63E-11 8.71E-12 4.37E-12 WSW 1.29E-10 4.20E-11 1.55E-11 8.26E-12 4.14E-12 w 1.22E-10 3.98E-11 1.47E-11 7.82E-12 3.92E-12 WNW 1.07E-10 3.48E-11 1.28E-11 6.84E-12 3.43E-12 NW 9.70E-11 3.16E-11 1.16E-11 6.20E-12 3.11E-12 NNW 1.41E-10 4.58E-11 1.69E-11 9.00E-12 4.52E-12 DIRECTION TO- SECTOR N = A E = E s = J w = N NNE = B ESE = F SSW = K WNW = p NE = C SE = G SW = L NW = Q ENE = D SSE = H WSW = M NNW = R Worst Case 0/Q = 4.46E-08 1/m2 in Sector A 2001

Information PMP-601 0-OSD-001 I Rev. 27 PaQe 81 of 92 OFF-SITE DOSE CALCULATION MANUAL Annual Evaluation of x /Q and D/Q Values For Page:

Attachment 3.17 All Sectors 81

1. Performed or received annual update of x /Q and D/Q values. Provide a description of what has been received.

I Signature Date Environmental Department (print name, title)

2. Worst x /Q and D/Q value and sector determined. PMP-601 0-OSD-001 has been updated, if necessary. Provide an evaluation.

I Signature Date Environmental Department (print name, title)

3. Review nuclide mix for gaseous and liquid release paths to determine if the dose conversion factor of total body is still applicable. Provide an evaluation.

I Signature Date Environmental Department (print name, title)

4. Approved and verified by:

I Signature Date Environmental Department (print name, title)

Information PMP-601 0-OSD-001 I Rev. 27 Page 82 of 92 OFF-SITE DOSE CALCULATION MANUAL Pages:

Attachment 3.18 Dose Factors 82- 83 DOSE FACTORS FOR NOBLE GASES AND DAUGHTERS*

TOTAL BODY SKIN DOSE GAMMA AIR BETA AIR DOSE FACTOR FACTOR DOSE FACTOR DOSE FACTOR Ki (DFBi) Li (DFSi) Mi (DFrJ Ni (DFPi) mrem m3 (mrem m 3 (mrad m3 (mrad m3 RADIONUCLIDE per µCi yr) per µCi yr) per µCi yr) per µCi yr)

Kr-83m 7 .56E-02 --- 1.93E+01 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11 E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51 E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03

• The Iisted dose factors are for radionuclides that may be detected in gaseous effluents, from Reg. Guide 1.109. Table B-1 .

Information PMP-601 0-OSD-001 I Rev. 27 PaQe 83 of 92 OFF-SITE DOSE CALCULATION MANUAL Pages: .18 Dose Factors 82- 83 DOSE FACTORS FOR RADIOIODINES AND RADIOACTIVE PARTICULATE, IN GASEOUS EFFLUENTS FOR CHILD* Ref. s .2.1eeanctff pi pi INHALATION FOOD & GROUND PATHWAY PATHWAY (mrem m 3 (mrem m2 sec RADIONUCLIDE per µCi yr) per µCi yr)

H-3 1.12E+03 1.57E+Q3#

P-32 2.60E+06 7.76E+10 Cr-51 1.70E+04 1.20E+07 Mn-54 1.58E+06 1.12E+09 Fe-59 1.27E+06 5.92E+08 Co-58 1.11E+06 5.97E+08 Co-60 7.07E+06 4.63E+09 Zn-65 9.95E+05 1.17E+10 Rb-86 1.98E+05 8.78E+09 Sr-89 2.16E+06 6.62E+09 Sr-90 1.01E+08 1.12E+11 Y-91 2.63E+06 6.72E+06 Zr-95 2.23E+06 3.44E+08 Nb-95 6.14E+05 4.24E+08 Ru-103 6.62E+05 1.55E+08 Ru-106 1.43E+07 3.01E+08 Aq-110m 5.48E+06 1.99E+10 1-131 1.62E+07 4.34E+11 1-132 1.94E+05 1.78E+06 1-133 3.85E+06 3.95E+09 1-135 7.92E+05 1.22E+07 Cs-134 1.01E+06 4.00E+10 Cs-136 1.71E+05 3.00E+09 Cs-137 9.07E+05 3.34E+10 Ba-140 1.74E+06 1.46E+08 Ce-141 5.44E+05 3.31E+07 Ce-144 1.20E+07 1.91E+08

• As Sr-90. Ru-106 and 1-131 analyses are performed, THEN use P1 given in P-32 for non listed radionuclides .

• The units for both H3 factors are the same. mrem m 3 per µCi yr

Information PMP-601 0-OSD-001 I Rev. 27 Paqe 84 of 92 OFF-SITE DOSE CALCULATION MANUAL Radiological Environmental Monitoring Program Pages:

Attachment 3.19 Sample Stations, Sample Types, Sample Frequencies 84- 87

[Ref. 5.2.lu. 5.2 .lw, 5.2.ls]

SAMPLE DESCRIPTION/ SAMPLE SAMPLE ANALYSIS ANALYSIS STATION LOCATION TYPE FREQUENCY TYPE FREQUENCY ON-SITE AIRBORNE AND DIRECT RADIATION (TLD) STATIONS ONS-1 (T-1) 1945 ft@ 18° from Plant Axis Airborne Particulate Weekly Gross Beta Weekly Gamma Isotopic Quart. Comp.

Airborne 1-131 Weekly Radioiodine TLD Quarterly Direct Radiation Quarterly ONS-2 (T-2) 2338 ft @ 48° from Plant Axis Airborne Particulate Weekly Gross Beta Weekly Gamma lsotooic Quart. Como.

Airborne 1-131 Weekly Radioiodine TLD Quarterly Direct Radiation Quarterly ONS-3 (T-3) 2407 ft @ 90° from Plant Axis Airborne Particulate Weekly Gross Beta Weekly Gamma Isotopic Quart. Comp.

Airborne 1-131 Weekly Radio iodine TLD Quarterly Direct Radiation Quarterly ONS-4 (T-4) 1852 ft. @ 118° from Plant Axis Airborne Particulate Weekly Gross Beta Weekly Gamma Isotopic Quart. Comp.

Airborne 1-131 Weekly Radioiodine TLD Quarterly Direct Radiation Quarterly ONS-5 (T-5) 1895 ft@ 189° from Plant Axis Airborne Particulate Weekly Gross Beta Weekly Gamma lsotooic Quart. Como.

Airborne 1-131 Weekly Radioiodine TLD Quarterly Direct Radiation Quarterly ONS-6 (T-6) 1917 ft@ 210° from Plant Axis Airborne Particulate Weekly Gross Beta Weekly Gamma Isotopic Quart. Comp.

Airborne 1-131 Weekly Radioiodine TLD Quarterly Direct Radiation Quarterly T-7 2103 ft @ 36° from Plant Axis TLD Quarterly Direct Radiation Quarterly T-8 2208 ft@ 82° from Plant Axis TLD Quarterly Direct Radiation Quarterly T-9 1368 ft@ 149° from Plant Axis TLD Quarterly Direct Radiation Quarterly T-10 1390 ft@ 127° from Plant Axis TLD Quarterly Direct Radiation Quarterly T-11 1969 ft@ 11° from Plant Axis TLD Quarterly Direct Radiation Quarterly T-12 2292 ft @ 63° from Plant Axis TLD Quarterly Direct Radiation Quarterly CONTROL AIRBORNE AND DIRECT RADIATION (TLD) STATIONS NBF 15.6 miles SSW Airborne Particulate Weekly Gross Beta Weekly New Buffalo, Ml Gamma lsotooic Quart. Como.

Airborne Radioiodine 1-131 Weekly TLD Quarterly Direct Radiation Quarterly SBN 26.2 miles SE Airborne Particulate Weekly Gross Beta Weekly South Bend, IN Gamma Isotopic Quart. Comp.

Airborne Radioiodine 1-131 Weekly TLD Quarterly Direct Radiation Quarterly DOW 24.3 miles ENE Airborne Particulate Weekly Gross Beta Weekly Dowagiac. Ml Gamma lsotooic Quart. Como.

Airborne Radioiodine 1-131 Weeklv TLD Quarterly Direct Radiation Quarterly COL 18.9 miles NNE Airborne Particulate Weekly Gross Beta Weekly Coloma, Ml Gamma lsotooic Quart. Como.

Airborne Radioiodine 1-131 Weekly TLD Quarterly Direct Radiation Quarterly

Information PMP-601 0-OSD-001 I Rev. 27 PaQe 85 of 92 OFF-SITE DOSE CALCULATION MANUAL Radiological Environmental Monitoring Program Pages:

Attachment 3.19 Sample Stations, Sample Types, Sample Frequencies 84- 87 SAMPLE DESCRIPTION/ SAMPLE SAMPLE ANALYSIS ANALYSIS STATION LOCATION TYPE FREQUENCY TYPE FREQUENCY OFF-SITE DIRECT RADIATION (TLD) STATIONS OFT-1 4.5 miles NE. Pole #B294-44 TLD Quarterly Direct Radiation Quarterly OFT-2 3.6 miles, NE, Stevensville TLD Quarterly Direct Radiation Quarterly Substation OFT-3 5.1 miles NE, Pole #B296-13 TLD Quarterly Direct Radiation Quarterly OFT-4 4.1 miles, E, Pole #B350-72 TLD Quarterly Direct Radiation Quarterly OFT-5 4.2 miles ESE, Pole #B387-32 TLD Quarterly Direct Radiation Quarterly OFT-6 4.9 miles SE, Pole #B426-1 TLD Quarter Iv Direct Radiation Quarter Iv OFT-7 2.5 miles S, BridQman Substation TLD Quarterly Direct Radiation Quarterly OFT-8 4.0 miles S, Pole #B424-20 TLD Quarterly Direct Radiation Quarterly OFT-9 4.4 miles ESE, Pole #B369-214 TLD Quarterly Direct Radiation Quarterly OFT-10 3.8 miles S, Pole #B422-99 TLD Quarterly Direct Radiation Quarterly OFT-11 3.8 miles S, Pole #B423-12 TLD Quarterly Direct Radiation Quarterly GROUNDWATER (WELL WATER) SAMPLE STATIONS W-1 1969 ft @ 11 ° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-2 2302 ft @ 63° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-3 3279 ft@ 107° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-4 418 ft@ 301° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-5 404 ft @ 290° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-6 424 ft@ 273° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-7 1895 ft@ 189° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W -8 1274 ft@ 54° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-9 1447 ft@ 22° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-10 4216 ft@ 129° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-11 3206 ft @ 153° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-12 2631 ft@ 162° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-13 2152 ft @ 182° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-14 1780 ft@ 164° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly Tritium Quarterly W-15 725 ft @ 202° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly NPDES well MW-12C Tritium Quarterly W-16 2200 ft @ 208° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly NPDES well MW-20 Tritium Quarterly W-17 2200 ft @ 180° from Plant Axis Groundwater Quarterly Gamma Isotopic Quarterly NPDES well MW-21 Tritium Quarterly

Information PMP-601 0-OSD-001 I Rev. 27 PaQe 86 of 92 OFF-SITE DOSE CALCULATION MANUAL Radiological Environmental Monitoring Program Pages:

Attachment 3 .19 Sample Stations, Sample Types, Sample Frequencies 84- 87 DRINKING WATER STJ St. Joseph Public Intake Sta. Drinking water Once per calendar Gross Beta 14 day Comp.

9mi. NE Day Gamma Isotopic 14 day Comp .

1-131 14 day Comp.

Tritium Quart. Como.

LTW Lake Twp. Public Intake Sta . Drinking water Once per calendar Gross Beta 14 dav Como .

0.6 mi. S Day Gamma Isotopic 14 day Comp.

1-131 14 day Como.

Tritium Quart. Comp SAMPLE DESCRIPTION/ SAMPLE SAMPLE ANALYSIS ANALYSIS STATION LOCATION TYPE FREQUENCY TYPE FREQUENCY SURFACE WATER SWL-2 Plant Site Boundary - South Surface Water Once per calendar Gamma Isotopic Month. Como.

- 500 ft. south of Plant Day Tritium Quart. Comp Centerline SWL-3 Plant Site Boundary - North Surface Water Once per calendar Gamma lsotocic Month. Como .

- 500 ft. north of Plant Day Tritium Quart. Comp.

Centerline SEDIMENT SL-2 Plant Site Boundary - South Sediment Semi-Ann. Gamma Isotopic Semi-Annual

- 500 ft. south of Plant Centerline SL-3 Plant Site Boundary - North Sediment Semi-Ann. Gamma Isotopic Semi-Annual

- 500 ft. north of Plant Centerline INGESTION - MILK Indicator Farms Milk Once every 1-131 per sample 15 days Gamma Isotopic cer sample Milk Once every 1-131 per sample 15 days Gamma Isotopic per samcle Milk Once every 1-131 per sample 15 days Gamma Isotopic per sample INGESTION - MILK Background Farm I I Milk I Once every 15 days I 1-131 I per samcle I Gamma Isotopic I per sample SAMPLE DESCRIPTION/ SAMPLE SAMPLE ANALYSIS ANALYSIS STATION LOCATION TYPE FREQUENCY TYPE FREQUENCY INGESTION - FISH **

ONS-N 0.3 mile N, Lake Michi an Fish - edible Vear Gamma lsoto ic ONS-S 0.4 mile S, Lake Michi an Fish - edible 2/ ear Gamma lsoto ic OFS-N 3.5 mile N, Lake Michi an Fish - edible 2/ ear Gamma lsoto ic OFS-S 5.0 mile S, Lake Michi an Fish - edible 2/ ear Gamma lsoto ic

Information PMP-601 0-OSD-001 I Rev. 27 Paqe 87 of 92 OFF-SITE DOSE CALCULATION MANUAL Radiological Environmental Monitoring Program Pages:

Attachment 3 .19 Sample Stations, Sample Types, Sample Frequencies 84- 87 INGESTION - FOOD PRODUCTS On Site ONS-G Nearest sample to Plant in the Food Products At time of Gamma Isotopic At time of highest D/Q land sector harvest harvest containing media.

ONS-V Broadleaf At time of Gamma Isotopic At time of veoetation harvest harvest Off Site OFS-G In a land sector containing Food Products At time of Gamma Isotopic At time of food products, approximately 20 harvest Harvest miles from the plant, in one of the less prevalent D/Q land sectors OFS-V Broad leaf At time of Gamma Isotopic At time of veoetation harvest harvest INGESTION - BROADLEAF IN LIEU OF GARDEN CENSUS OR IN LIEU OF MILK(*)

3 samples of different kinds of broad leaf vegetation Broad leaf Monthly Gamma Isotopic Monthly collected at the site boundary, within five vegetation when available 1131 when available miles of the plant, in each of 2 different sectors with the highest annual average D/Q containing media 1 background sample of similar vegetation Broadleaf Monthly Gamma Isotopic Monthly grown 10-20 miles distant in one of vegetation when available 1131 when available the less prevalent wind directions.

Collect composite samples of Drinking and Surface water at least daily. Analyze particulate sample filters for gross beta activity 24 or more hours following filter removal. This will allow for radon and thoron daughter decay . If gross beta activity in air or water is greater than 10 times the yearly mean of control samples for any medium, perform gamma isotopic analysis on the individual samples.

• 1F at least three indicator milk samples and one background milk sample cannot be obtained, THEN three broad leaf samples of different kinds will be collected in each of 2 different offsite locations, within five miles of the plant, with the highest D/Q (refers to the highest annual average ground D/Q). Also, one background broad leaf sample of similar kinds will be collected 10 to 20 miles from the plant in one of the less prevalent D/Q land sectors.

The three milk indicator and one background farm will be determined by the Annual Land Use Census and those that are willing to participate .

IF it is determined that the milk animals are fed stored feed, THEN monthly sampling is appropriate for that time period.

Evaluate samples that identified positive plant effluent related radionuclides and determine if additional analysis are necessary to identify hard to detect radionuclides. The 10 CFR 61 scaling factor report should be consulted along with the radioactive material shipping program owner and the ODCM program owner to assist with this determination .

• • Due to the transient nature of fish throughout the year due to lake temperatures and food supplies, it is acceptable to obtain fish sample from alternate locations so long as the intent of sampling fish from close to the plant site and samples of fish serving as a background exist.

Information PMP-601 0-OSD-001 I Rev. 27 I Paqe 88 of 92 OFF-SITE DOSE CALCULATION MANUAL Pages:

Attachment 3 .20 Maximum Values for Lower Limits of Detections A,B - REMP 88 - 89

[Ref. 5.2 .1u]

Radionucl ides Food Product Water Milk Air Filter Fish Sediment pCi/kg, wet pCi/1 pCi/1 pCi/m 3 pCi/kg, wet pCi/kg, dry Gross Beta 4 0.01 H-3 2000 Ba-140 60 60 La-140 15 15 Cs-134 60 15 15 0.06 130 150 Cs-137 60 18 18 0.06 150 180 Zr-95 30 Nb-95 15 Mn-54 15 130 Fe-59 30 260 Zn-65 30 260 Co-58 15 130 Co-60 15 130 1-131 60 1 1 0.07 This Data is directly from our plant-specific Technical Specification.

Information PMP-601 0-OSD-001 I Rev. 27 I Pacie 89 of 92 OFF-SITE DOSE CALCULATION MANUAL Pages: .20 Maximum Values for Lower Limits of Detections A,B - REMP 88 - 89 NOTES A. The Lower Limit of Detection (LLD) is defined as the smallest concentration of radioactive material in a sample that will be detected with 95% probability and 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation), the LLD is given by the equation:

LLD= 4.66a

• S E

• V

• 2.22

• Y

• e(-..*~)

Where LLD is the a priori lower limit of detection as defined above (as pCi per unit mass or volume) . Perform analysis in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering radionuclides, or other uncontrollable circumstances may render these LLDs unachievable. It should be further clarified that the LLD represents the capability of a measurement system and not as an after the fact limit for a particular measurement.

S is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute) .

E is the counting efficiency of the detection equipment as counts per transformation (that is, disintegration)

V is the sample size in appropriate mass or volume units 2.22 is the conversion factor from picocuries (pCi) to transformations (disintegrations) per minute Y is the fractional radiochemical yield as appropriate

"- is the radioactive decay constant for the particular radionuclide

~t is the elapsed time between the midpoint of sample collection (or end of sample collection period) and time of counting.

B. Identify and report other peaks which are measurable and identifiable, together with the radionuclides listed in Attachment 3.20, Maximum Values for Lower Limits of Detections A,B - REMP.

a A 2. 71 value may be added to the equation to provide correction for deviations in the Poisson distribution at low count rates, that is, 2.71 + 4.66 x S.

Information PMP-601 0-OSD-001 I Rev . 27 PaQe 90 of 92 OFF-SITE DOSE CALCULATION MANUAL Reporting Levels for Radioactivity Concentrations Page:

Attachment 3 .21 in Environmental Samples 90 Radionuclides Food Product Water Milk Air Filter Fish pCi/kg, wet pCi/1 pCi/1 pCi/m 3 pCi/kg, wet H-3 20000 Ba-140 200 300 La-140 200 300 Cs-134 1000 30 60 10 1000 Cs-137 2000 50 70 20 2000 Zr-95 400 Nb-95 400 Mn-54 1000 30000 Fe-59 400 10000 Zn-65 300 20000 Co-58 1000 30000 Co-60 300 10000 1-131 100 2 3 0.90 IF any of the above concentration levels are exceeded THEN see guidance contained in step 3.5 .2a. for additional information .

Information PMP-601 0-OSD-001 I Rev. 27 Paqe 91 of 92 OFF-SITE DOSE CALCULATION MANUAL Page: .22 On-Site Monitoring Location - REMP 91 ONS-South ONS-North TLC T-6 TLD T-5 Air ONS- Air ONS-5 Surface Water 6 SWL-2

---

.._~

Sediment SL-2 Well W-16 TLD T-3 AirONS-3 Well W-10 LEGEND ONS ONS-6: Air Sampling Station T T-12: TLD Sampling Station W W-17: REMP Groundwater Wells SWL- 2, 3: Surface Water Sampling Stations SL-2 SL-3: Sediment Sampling Stations ONS-N & S: Fish sampling locations

Information PMP-601 0-OSD-001 I Rev. 27 PaQe 92 of 92 OFF-SITE DOSE CALCULATION MANUAL Page: .23 Off-Site Monitoring Locations - REMP 92

( Coloma Legend D Substation Offsite REMP Monitoring Locations c-,.....

Coloma Rd OFT OFT-11: TLD Locations Background Air/TLD Stations Drinking Water Locations Indicator Milk Farm Locations Twelve r ...

Background Milk Farm Locations OFS Offsite Fish locations \ / 20 Mile Radius Millburg St Joseph Water Treatment Plant OFS-North (STJ)

J

\~ Dowagiac Substation

Background

Air/TLD Sodus (DOW)

TLD OFT-3 \ M-51 Colby St TLDOFT-1 TLD OFT-2

\

TLD OFT-4 TLD OFT-9 TLDOFT-5 *

l--,

TLD OFT-7 TLD-OFT-10 TLDOFT-11 TLDOFT-8 TLDOFT-6 OFS-South Cleveland Rd Union Pier New Buffalo Substation Background Three Air/TLD Oaks us 12 Laporte Background Milk Farm

' l Hwy2 Hwy35 ~ ,

Kankakee Station

Background

Hwy23 Air/TLD (SBN)

REVISION

SUMMARY

Procedure No.: PMP-601 0-OSD-001 Rev. No.: 27

Title:

OFF-SITE DOSE CALCULATION MANUAL Alteration Justification 10 CFR 50.59 is not applicable to this procedure revision. Per definition in Attachment 1 of PMP-2010-PRC-002. This is an administrative procedure governing the conduct of facility operations. Changes to this document are made in accordance with Technical Specification 5.5.1 and implemented through 12-EA-6090-ENV-114, Effectiveness Review for ODCM/PCP Programs.

Security review per PMP-2060-SEC-007 is not applicable to this procedure revision. All review responses of the pre-screening in Data Sheet 1 of PMP-2060-SEC-007 were "No" and peer reviewed per Step 3.3.1.

Section 1.0 - Added note informing users This is an editorial change to ensure users that the revision reflects the completed RMS understand that the transition of the RMS Project changes to upgrade the system to replacement project to the new Mirion Mirion detectors. equipment has completed, and old equipment referenced in past revisions were removed.

GT-2020-0319 Revised Table of Contents and renumbered Multiple Sections and Attachments required as needed; no margin marks used. updating of titles and/or updating the contents contained inside which lengthened the documentation. This altered page numbering throughout.

3. 3 .1- Revised the step to reflect the Editorial correction to remove old equipment completed replacement of detectors (Mirion). guidance now that the new detectors are Updated Attachment Titles as needed. installed. No changes to intent made, and Margin marks used on affected sub-steps. Titles revisions made to reflect the changing attachments. Added Note to clarify the naming of RRS-1001-B/1021-B and explain why the difference existed from other plant documentation. Both are equivalent and point to the same single component.

3.3.2- Revised the step to reflect the Editorial correction to remove old equipment completed replacement of detectors (Mirion). guidance now that the new detectors are Updated Attachment Titles as needed. installed. No changes to intent made, and Margin marks used on affected sub-steps. Titles revisions made to reflect the changing attachments 5.2- Removed Eberline references and re- Editorial correction to remove equipment lettered the step as needed. references no longer applicable in this revision.

Office Information for Form Trackin_q Only - Not Part of Form This is a free-form as called out in PMP-2010-PRC-002, Procedure Alteration, Review, and Approval . Page 1 of 5

REVISION

SUMMARY

Procedure No.: PMP-6010-OSD-001 Rev. No.: 27

Title:

OFF-SITE DOSE CALCULATION MANUAL Alteration Justification .2- Rewritten to include Mirian Editorial correction to remove old equipment information while removing old monitor guidance now that the new detectors are data. Updated guidance and provided installed as well as make clarifications on corrections on associated actions. No margin actions requiring independent samples taken.

marks used. AR#2019-7934 .3- Rewritten to include Mirian Editorial correction to remove old equipment information while removing old monitor guidance now that the new detectors are data. Updated guidance and provided installed as well as make clarifications on corrections on associated actions. No margin when alarm annunciations are expected to marks used. occur. .4- Rewritten to include Mirian Editorial correction to remove old equipment information while removing old monitor guidance now that the new detectors are data. Updated guidance and provided installed and updated equipment labels.

corrections on associated actions. No margin Specific guidance updated for local display marks used. units and computer based data displays (PPC/RadServe).

AR#2019-9650 , AR#2020-4600 .5- Rewritten to include Mirian Editorial correction to remove old equipment information while removing old monitor guidance now that the new detectors are data. Updated guidance and provided installed, adding updated equipment ID corrections on associated table notations. No information .

margin marks used. AR#2019-9650 .8- Rewritten to include Mirian Removed old Eberline detector instruments, information while removing old monitor with no changes made to MRP or flowrates data. No margin marks used. as these remain unaffected by the RMS project. .11- Removed old tables and Editorial correction to remove old equipment notes pertaining to the Eberline monitors. No guidance, removing the old detector margin marks used. efficiency data. .12- Removed old tables and Editorial correction to remove old equipment notes pertaining to the Eberline monitors. guidance, removing the old detector Updated the detector efficiencies for DRA- efficiency data. Updated the blowdown 300/DRA-353 for 4 pi shielding. No margin detector efficiencies for the new 4 pi marks used. shielding.

Office Information for Form Trackin_q Only - Not Part of Form This is a free-form as called out in PMP-2010-PRC-002, Procedure Alteration, Review, and Approval. Page 2 of 5

REVISION

SUMMARY

Procedure No. : PMP-6010-OSD-001 Rev. No.: 27

Title:

OFF-SITE DOSE CALCULATION MANUAL Alteration Justification .13- Retitled the Attachment to Editorial correction to remove old equipment remove reference to the old Eberline guidance, removing the old detector monitors . Removed old tables and notes efficiency data.

pertaining to the Eberline monitors. No margin marks used.

Office Information for Form Trackin_Q Only - Not Part of Form This is a free-form as called out in PMP-2010-PRC-002, Procedure Alteration, Review, and Approval. Page 3 of 5

REVISION

SUMMARY

Procedure No.: PMP-6010-OSD-001 Rev. No.: 27

Title:

OFF-SITE DOSE CALCULATION MANUAL IMPLEMENTATION PLAN Summary of Change See Revision Summary for details.

Reason for Change See Revision Summary for details.

Implementation Schedule Procedure to be made effective following PORC and upon Plant Manager's approval.

Training Needs N/A Expiration Date N/A Required Basis Documents Update None Related Processes and Procedures 12-THP-6010-RPl-805, Radiation Monitoring System Setpoints 12-THP-6010-RPP-709, Radiation Monitoring System Liquid Effluent Alarm .

These procedures are being updated to reflect the new Mirion monitors and their efficiencies as noted in this procedure. Changes are being tracked by GTs entered in the Corrective Action Program .

Transition Plan Attachments from previous revision of 12-THP-6010-OSD-001 may be used subject to the cond itions described in PMP-2010-PRC-003. The actual equipment transition occurred with the previous revision, and this revision primarily is cleaning up the old uninstalled equipment references and guidance now that the Project has been RTO'd to Operations .

Related Equipment Modifications Installation of new Mirion radiation monitors in both units per EC-53363 and EC-53364.

Communication Plan Effective date of this revisions will be communicated via email to interested groups.

Special Tools, Aids, Permits, Etc.

N/A Related Condition Reports GT 2020-4600; GT-2020-0319; GT 2019-7934; AR-2019-9650 Office Information for Form Trackin_q Only - Not Part of Form This is a free-form as called out in PMP-2010-PRC-002, Procedure Alteration, Review, and Approval. Page 4 of 5